IR 05000361/1999301: Difference between revisions

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{{Adams
{{Adams
| number = ML20195H603
| number = ML20199E879
| issue date = 06/11/1999
| issue date = 01/13/1999
| title = Forwards Exam Repts 50-361/99-301 & 50-362/99-301 Administered at Facility on 990416,with as Given Written Exam Attached
| title = Informs That During 990112 Telcon Between Mk Rauch & J Pellet,Arrangements Were Made for Administration of Written Retake License Exams 50-361/99-301 & 50-362/99-301 at San Onofre,During Wk of 990308
| author name = Hurley L
| author name = Pellet J
| author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
| author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
| addressee name =  
| addressee name = Ray H
| addressee affiliation = NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
| addressee affiliation = SOUTHERN CALIFORNIA EDISON CO.
| docket = 05000361, 05000362
| docket = 05000361, 05000362
| license number =  
| license number =  
| contact person =  
| contact person =  
| document report number = 50-361-99-301, 50-362-99-301, NUDOCS 9906170095
| document report number = 50-361-99-301, 50-362-99-301, NUDOCS 9901210109
| document type = INTERNAL OR EXTERNAL MEMORANDUM, MEMORANDUMS-CORRESPONDENCE
| document type = CORRESPONDENCE-LETTERS, OUTGOING CORRESPONDENCE
| page count = 1
| page count = 4
}}
}}


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=Text=
=Text=
{{#Wiki_filter:. . . . - . . . . - . -
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j#    UNITED STATES I
[ , ,  NUCLEAR REGULATORY COMMISSION
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==REGION IV==
I
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  #' "'44 9  UNITED STATES
  %, l pe  61' .tYAN PLAZA DRIVE, sulTE 400 ,
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%,,,  AhLINGTON, TEXAS 760114064  i June 11,1999 NOTE TO: NRC Document Control Desk    l Mail Stop O-5-D-24    I FROM: Laura Hurley, Licensing Assistant Operations Branch, Region IV i
t ,
SUBJECT: OPERATOR LICENSING WRITTEN RETAKE EXAMINATIONS ADMINISTERED ON APRIL 16,1999, AT SAN ONOFRE NUCLEAR GENERATING STATION, UNITS 1 AND 2.
NUCLEAR REGULATORY COMMISSION
 
  $ f  REGloN IV 611 RYAN PLAZA drive, SUITE 400
l l
DOCKETS #50-361; 50-362 On April 16,1999, Operator Licensing Examinations were administered at the referenced facility. Attached you will find the following information for processing through NUDOCS and distribution to the NRC staff, including the NRC PDR:
Item #1 - Facility submitted outline and the initial written exam submittal for distribution under RIDS Code A070.
 
Item #2 - Examination Report with the as given written examination attached, j designated for distribution under RIDS Code IE42. {
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If you have any questions, please contact Laura Hurley, Licensing Assistant, Operations Branch, Region IV at (817) 860-8253. I l
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9906170095 990611 PDR ADOCK 05000361 V  PDR _
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" "'%,y   UNITED STATES
y g  ARLINGTON, texas 76011-8064 January 13,1999 l Harold B. Ray, Executive Vice President Southern California Edison Co.
  &  NUCLEAR REGULATORY COMMISSION    l e '
o      i
% 1 g   REGloN IV    !
' %. q  611 RYAN PLAZA DRIVE, sulTE 400 4   ARLINGTON, TEXAS 76011-8064 y,g WAY - 61999    !
        !
Harold B. Ray, Executive Vice President Southern California Edison Co.


San Onofre Nuclear Ger;erating Station P.O. Box 128     i San Clemente, California 92674-0128     l SUBJECT: NRC INSPECTION REPORT 50-361; 50-362/99-301
San Onofre Nuclear Generating Station P.O. Box 128 San Clemente, California 92674-0128 SUBJECT: NRC INSPECTION REPORT 50-361/99-301; 50-362/99-301
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==Dear Mr. Ray:==
==Dear Mr. Ray:==
On April 16,1999, an operator licensing certification inspection was conducted at your San Onofre Nuclear Generating Station. The enclosed report presents the scope and results of that inspection.
In a telephone conversation on January 12,1999, between Messrs. K. Rauch and J. Pellet,  j arrangements were made for the administration of written retake licensing examinations at San
 
  , Onofre, during the week of March 8,1999.
The inspection included an evaluation of four applicants for an operator license (two operators and two senior operators). This was a licensee-authored retake written examination only and did not involve an NRC site visit. We determined that the four applicants satisfied the requirements of 10 CFR Part 55, and the appropriate licenses have been issued.
 
The written examination was adequate for administration as submitted. Minor enhancement comments to a number of questions were adequately addressed by your staff.
 
In accordance with 10 CFR 2.790 of the NRC's " Rules of Practice," a copy of this letter and its J '
enclosure will be placed in the NRC Public Document Room (PDR). 1 q \
Should you have any questions concerning this inspection, we will be pleased to discuss them I with you.
 
Sin ely, I
f Arthur T. Howel*lli, Director Division of Reactor Safety Docket Nos.: 50-361;50-362 License Nos.: NPF-10; NPF-15-q405l20010    $W
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. Southern California Edison Co. -2-
 
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===Enclosure:===
' .NRC Inspection Report
> 50-361; 50 362/99-301
_
 
REGION IV==
Docket Nos.: 50-361; 362  i l
    '
License Nos.: NPF-10; NPF-15 Report No.: 50-361;362/99-301 Licensee: Southern California Edison Co.
 
Facility: San Onofre Nuclear Generating Station Location: P.O. Box 128 San Clemente, California 92674-0128 Dates: April 16,1999 Inspector: John L. Pellet, Chief, Operations Branch l Approved By: Arthur T. Howell lil, Director Division of Reactor Safety ATTACHMENTS:
  ' Attachment 1: Supplemental Information Attachment 2: Final Written Examination and Answer Key
    .
 
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EXECUTIVE SUMMARY San Onofre Nuclear Generating Station  i NRC Inspection Report 50-361; 362/99-301 NRC examiners. evaluated the competency of four operator license applicants for issuance of operating licenses at the San Onofre Nuclear Generating Station. The licensee developed the retake written examination using NUREG-1021, Interim Revision 8, January 1997. NRC ;
examiners reviewed, and approved the examination. The written examination was administered on April 16,1999, by facility proctors in accordance with the guidance in NUREG 1021, Interim Revision 8.
 
Qgggtions
*- The two reactor operator and two senior operator license applicants passed the examination (Section 04.1).
 
* The test material was adequato for administration as submitted, with no post-examination changes identified (Section 05.1).
 
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3-Report Details i
Summary of Plant Status The plant operated at essentially 100 percent power for the duration of this inspection.
 
l. Operations 04 Operator Knowledge and Performance 04.1 Initial Written Examination
      ]
I a.- Inspection Scoce On April 16,1999, the facility licensee proctored the administration of the written examination approved by the NRC to the two individuals who had reapplied for a reactor operator (RO) and two who had applied for senior operator (SRO) licenses. The
-
licensee proposed grades for the written examinations and evaluated the results for question validity and generic weaknesses. The examiner reviewed the licensee's results.
 
b. Observations and Findinas
      '
The minimum passing score was 80 percent. The candidates' scores for the written examination ranged from 88 to 94 percent. The average score was 90. The licensee's post-administration analysis identified that the administered examination was acceptable. There were no post-examination comments or changes to the written examination recommended by the licensee or identified by examiner review of the results. Licensee review of the examination results indicated several questions identified potential validity or training deficiencies for further internal review. The i specific questions identified were common RO/SRO questions 1,37,39,52, and 69; RO questions 82,95,96, and 99; and SRO only questions 83,85,86,87,92,96,98, and 99 (shown in Attachment 2 as questions 108,110,111,112,118,123, and 124). The licensee found all questions appropriate and valid. The examiner reviewed this analysis and the specific questions and determined that the issues were narrowly focused within various systems, such as auxiliary feedwater, procedure immediate actions f rom memory, annunciators, and technical specifications, and did not represent generic weaknesses, c. Conclusions -
The four applicants passed the written examination. No broad knowledge or training weaknesses were identified as a result of evaluation of the graded examination.
 
<
 
-05
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Operator Training and Qualification 05.1. Initial Licensina Examination Devetooment The facility licensee developed the initial licensing examination in accordance with guidance provided in NUREG 1021," Operating Licensing Examinatica Standards,"
Interim Revision 8, dated January 1997.
 
05.1.1 Examination Outline a. insoection Scope -
The facility licensee submitted the initial examination outlines on January 14,1999. The
. chief examiner reviewed the submittal against the requirements of NUREG-1021, Interim Revision 8.
 
b. Observations and Findinas The chief examiner determined that the initial examination outlines satisfied NRC requirements.
 
c. Conclusions
~The licensee submitted an adequate examination outline.
 
05.1.2 Examination Packaae a. Insoection Scope The draft examination was transmitted by the licensee to the NRC on March 29,1999.
 
The licensee submitted the completed final examination pr.ckage on April 5,1999. The chief examiner reviewed the examination against the requirements of NUREG-1021, Interim Revision 8.
 
b. Observations and Findinas The draft written exarninations each contained 100 questions, The draft examinations were technically valid, discriminated at the proper level, and responsive to the outline submitted by the licensee. The written examination was considered adequate for administration, as submitted. The examiner developed clarificat, ion or enhancement comments on about one fourth of the questions. The licensee staff incorporated these comments and all proposed enhancements were accepted by the examiner. In contrast to the prior examination (see NRC Inspection Report 50-361; -362/98-302), the submitted examination demonstrated improved question stem focus and distractor
' credibility. .The quality of the submitted examination was reflected in the lack of post-administration changes, especially as compared to the prior examination, for which the license requested changes to a significant number of the questions.
 
.
 
I-5-c. - Conclusions      4
  .  . l The test material was adequate for administration as submitted by the licensee. No i changes to examination materials were required as a result of administration.
 
V. Manaaement Meetinas X1 Exit Meeting Summary The chief examiner telephonically presented the inspection results to the licensee staff at the conclusion of the inspection on May 3,1999. The licensee acknowledged the
      -
findings presented.
 
'
 
The licensee did not identify as proprietary any information or materials examined during this inspection.
 
,
 
...
ATTACHMENT 1 SUPPLEMENTAL INFORMATION PARTIAL LIST OF PERSONS CONTACTED Licensee
' K. Rauch, Operations Training Supervisor NRC None I
INSPECTION PROCEDURES USED  1 NUREG-1021, NUREG-1021, " Operating Licensing Examination Standards," Interim Revision 8, January 1997  l
 
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ATTACHMENT 2 FINALWRITTEN EXAMINATION AND ANSWER KEY
 
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ATTACHMENT 2 FINAL WRITTEN EXAMINATION AND ANSWER KEY
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COMPOSITE  i NRC EXAM KEY .
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Question #1 Given the following plant conditions:
  -
Unit 2 is operating at 100% power
  -
All CEAs are fully withdrawn to the Upper Electrical Limit
  -
RSPT#1 for CEA 46 to CEAC #1 reads 140" Which CPC/CEAC annunciator display light should be illuminated?
A. '
CEAC FAIL B. CEA DEV.
 
C. CEAC INOP.
 
D. CEAC SENS FAIL.
 
Answer B Exam Level 8 Cognitive Level Memory Facility San Onofre 2 & J Exam Date 4/16/99 Tier:(1) . 001 ak2.05 Rod motion lights  RO Group: 2 SRO Group: 1 RO K/A 2.9 SRO K/A 3.1 Reference Title - Facility Reference Number Section Page Revision Learning Obj.
 
Core Protection /CEAC SO23-3-2.13 Att.10 107 10 Reference Title Operation Material Required for Examination Question Source: New
    .
 
e Question #2 -
De following plant conditions exist:.      1
-
The plant has tripped
  '
  -
All systems actuated as expected with the exception of the following:
  -
CEAs 40 and 41 are stuck fully withdrawn
  --
The operating charging pump has tripped on a loss of suction pressure
  -
Operators are unable to start any charging pumps Which of tiie following operator actions is procedurally required under these conditions?
A. Lower RCS pressure and borate via HPSI.
 
B. Borate via gravity feed suction path.    .
        !
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C. Initiate RCS cooldown and initiate SIAS. I
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D. Stabilize RCS temperature and pressure until boration is initiated.
 
'
Answer A Exam Level . B Cognitrve Level Comprehension Facihty San Onofre 2 & 3 Exam Date 4/16,a99 Tier: (2) 001 k 4.05 Boration and Diluton RO Group: 1 SRO Group: 1 RO K/A 3.9 SRO K/A3.9 ;
Reference Title  Facility Reference Number Section Page Revison Learning Obj.
 
Emergency Boration SO23-13-11  5 4 6552 Material Required for Examination Question Source: New
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o r
Question #3 Which one of the following is the reason for not starting the fourth Reactor Coolant Pump until RCS temperature is greater than 500 degrees Fahrenheit?
A. To prevent exceeding RCS heatup rate limits.
 
B. To prevent excessive RCP starting currents.
 
C. To prevent Steam Generator tube stresses.
 
D. ~ To prevent core uplift.
 
Answer D Exam Level B Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/18/99 Tier: ( 2) 002 K6.02 RCP  RO Group: 2 SRO Group: 2 RO K/A 3.6 SRO K/A 3.8 Refererte Title  Facility Reference Number Section Page Revision Learning Obj.
 
!
Plant S/U from CSD to HSB SO23-5-1.3  Att.16 118 19 gg j Material Required for Examination Question Source: New
 
r Question #4 The following conditions exist:
  -
Unit 2 at 85% power, ,
  -
Recovery of a dropped CEA (#20) is in progress.
 
- . Group 6 is at 149 inches withdrawn.
 
-
CEA #20 (a Group 6 CEA) is at 100 inches withdrawn.
 
-
CEA #1 (a Group 2 CEA) drops fully into the core.
 
Which of the following is/are the correct required action (s)?
A. Continue realigning CEA # 20, then align CEA # 1.
 
B. Realign CEA # 1, then continue aligning CEA # 20.
 
C. Manually trip the reactor.-
        *
D. Reduce turbine load to maintain Tc within the operating band.
 
Ansacr C Exarn Level B- Cognitive Level Cornprehension - Facility San Cnofre 2 & 3 Exam Date 4/16/99 Tier:(1) 003 akt.03 Relationship of reactivity and reactor power to RO Group: 2 SRO Group: 1 rod motiort.
 
__
RO K/A 3.5 SRO K/A 3.8 Reference Title Facility Reference Nurnber Section Page Revision Learning Ob..
Misationed cEA - So23-13-13  4 4 6565 Material Required for Examination Question Source: New f
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Question #5 Given the following Unit 2 conditions:
-. Reactor tripped from i_00% power
-
Pressurizer pressure - 1870 psia
-
Containment pressure - 3.8 psig To where is RCP bleedoff flow being directed?
A. He VCT.
 
B. Re Quench Tank.
 
C. De Containment Sump.
 
D. The RCDT.
 
Answer B Exam Level B Cognitive Level Memory  Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier:(2) 003 k6.04 Containment isolation v6tves aflecting RO Group: 1 SRO Group: .1 operation.
 
RO K/A 2.8 SRO K/A 3.1 '
Reference Title Facildy Reference Number Section Page Revision Learning Obj.
 
CVCS  PalD 40124A    23 9210.
 
Material Required for Examination Question Source: NRC i1/98
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. Question #6
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Given the following plant conditions on Unit 3:
  -
Plant is in a normal full power alignment
  -
Pressurizer level is 43%
  -
Pressurizer level setpoint is 48%
Which of the following is the expected automatic response of the CVCS system?
A. Three charging pumps'in service and letdown flow at maximum.
 
B. One charging pump in service and letdown flow at minimum.


C. One charging pump in service and letdown flow at maximum.
As agreed during the telephone conversation, your staff will prepare the examinations based on the guidelines in Revision 8, of NUREG-1021," Operator Licensing Examination Standards for Power Reactors." The NRC regional office will discuss with your staff any changes that might be necessary before the examinations are administered.


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D. Three charging pumps in service and letdown flow at minimum.
To meet the above schedule, it will be necessary for your staff to furnish the examination outlines by January 21,1999. The written examinations and the supporting reference
 
Answer D Exam Level B Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (2) 004 A1.04 Pzr pressure and level  RO Group: 1 SRO Group: 1 RO K/A 3.9 SRO K/A 4.1 Reference Title Facility Reference Number . Section Page Revision Learning Obj.
 
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Pressurizer Pressure SO23-31.10  Att. 2 18 8 and Level Control      6706 Material Required for Examination Question Source: Bank
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Question #7 The plant is at 75% power when a new Purification Demineralizer is placed in service. Which of the following will occur if the boron saturation of this demineralizer is incomplete?
A. T-ave will increase.
 
B. Reactor power will decrease.
 
C. Lithium concentration will go up.
 
D. Demineralizer resin channeling.
 
Answer A Exam Level B Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (2) 004 k5.15 , Boron and control reactivity effects as they RO Group: 1 SRO Group: 1 relate to MTC.
 
RO K/A 3.3 SRO K/A 15 Reference Tdle Facility Reference Number Secton Page Revision Learning Obj.
 
RCS Purstcaton and SO23-3-2.4  Att. 6 36 10 67j7 Deborating ton Exchanger Operation Material Required for Examination Question Source: New
 
Question #8 Given the following plant conditions:
-
Plant is at 100% power, all rods out
-
Subsequently, CEA 3 (SD Bank A) drops into the core Which of the following is the reason for reactor power to be reduced below 90%?
A. To minimize radial power peaking.
 
B. To prevent adverse Axial Shape index.
 
C. . To prevent a CPC generated Reactor Trip.
 
D. To ensure Transient insertion Limits are not exceeded.
 
Answer A Exam Level B CognitiveLevel Memory  Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier:(1) 005 ak106 Bases for power limit, for rod misalignment. RO Group: 1 SRO Group: 1 RO K/A 2.9 SRO K/A 3.8 Reference Title Facihty Reference Number Section Page Revision Learning Ott Technical  Reactivity Control Systems LCS 3-1- 3-1.105.7 Specitcatens 6565 105  i Material Required for Examination Question Source: New
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f-Question #9 A hot leg vent is required whenever the Steam Generator Nozzle Dams are installed. Which of the following states a reason for this if a less of Shutdown Cooling (SDC) were to occur?
A. To prevent steam buildup in the hot leg which could cause a loss of natural circulation.
 
B. To prevent steam buildup in the hot leg which will ultimately collapse, causing severe water hammer.
 
C. To prevent RCS pressurization lesding to a failure of the cold leg nozzle dam and potential core uncovery.
 
D. To prevent RCS pressurization from causing an erroneous Draindown level Monitoring System (DLMS) indication.
 
Answer C Exam Level B Cognitive Level Memory Facihty San Onotre 2 & 3 Exam Date 4/16/99 Tier: (2) 005 k3.01 RCS  RO Group: 3 SRO Group: 3 RO K/A 3.9 SRO K/A 3.9 Reference Title Facihty Reference Number Secten Page Revision Loarning Obj.
 
Draining the RCS SO23-3-1.8  Att. 21 159 13 3366 Material Required for Examination Question Source: New L
 
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Question #10 An RCS HOT LEG break has just occurred on Unit 2.
:
 
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What would be the result if the E01 steps to initiate simultaneous hot / cold leg injection were performed immediately following the LOCA diagnosis?
materials identified in Attachment 2 of ES-201 will be due by March 1,1999. Any delay in j
        !
A. Inadequate Core Cooling due to the loss of Safety Injection flow out of the l break.
 
]
B. The HPSI pumps would reach runout conditions.
 
l C. Boration flow would be inadequate to maintain Shutdown Margin requirements. !
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D. Injection flow through the core would be stopped.
 
l Answer A Exam Level B Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99
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Tier: ( 2) 006 K.3.01 RCS  RO Group: 2 SRO Group: 2
receiving the required examination and reference materials, or the submittal of inadequate or incomplete materials, may cause the examinations to be rescheduled.  ;
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l in order to conduct the requested written examinations, it will be necessary for your staff to l provide adequate space and accommodations in accordance with ES-402.
RO K/A 4.1 SRO K/A 4.2 Reference Title Facihty Reference Number Secton Page Revision Learning Obj.
 
LOCA Bases SO23-14-3  Att.1 74 4   i 6893 Material Required for Examination Question Source: Bank
 
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Question #11 Given the following plant conditions:
  -
Plant tripped 30 minutes ago
  - Pressurizer Safety Valve is lifting
  -
Pressurizer pressure is 1900 psia
  -
RCS Tu is 545 F.
 
-
Quench Tank rupture disk has ruptured
  - Containment Pressure is I psig What is the expected temperature in the tailpipe downstream of the affected Pressurizer Safety Valve?
A. 215 degrees F.


B. 300 degrees F.
Appendix E of NUREG-1021 contains a number of NRC policies and guidelines that will be in effect while the written examinations are being administered.


'
To permit timely NRC review and evaluation, your staff should submit preliminary reactor  l
C. 545 degrees F.
 
D. 628 degrees F.
 
Answer A Exam Level B Cognitive Level Appleation Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (2) 007 a2.01 Stuck open safety. RO Group: 3 SRO Group: 3 RO K/A 3.9 SRO K/A 3.9 Reference Title Facility Reference Number Section Page Revisioit Learning Obj.
 
Steam Tables Mollier Diagram    4068 {
Material Required for Examination Steam Tables Question Source: New l
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Question #12 Given the following:
-
Component Cooling Water (CCW) Pumps P-024 and P-026 are operating
-
P-025 is aligned to Train A and is in standby
-
  . A Safety Injection Actuation Signal (SIAS) and a Loss of Voltage Signal (LOVS)
occurred on both safety related buses.
 
-
_ Both safety related buses have been reenergized from their respective Emergency Diesel Generators (EDGs).
 
Which of the following correctly describes how the CCW pumps automatically respond to the conditions described?
A. All CCW pumps start.
 
B. P-024 and P-026 start; P-025 does not start.
 
C. P-024 and P-025 start; P-026 does not start.
 
D. P-025 and P-026 start; P-024 does not start.
 
Answer D Exam Level B Cognitive Level Application Facihty San Onofre 2 & 3 Exam Date 4/16/99 Tier: (2) 008 a2.01 Loss of CCW Pump  RO Group: 3 SRO Group: 3 RO K/A 3.3 SRO K/A 3.3 Reference Title Facility Reference Number Section Page Revision Learning Obj.
 
Lossof CCW/SyVC 5023-13-7  3.5 5 3 5370 l- Material Required for Examination l Question Source: NRC 6/98 l
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Question #13 Which of the following Design Basis Accidents would generate the GREATEST amount of hydrogen and the reason why?
A. SMALL BREAK LOCA, due to increased heat input from the mnning RCPs.
 
B. LARGE BREAK LOCA, due to greater steam voiding in the core.
 
C. SMALL BREAK LOCA, due to less steam voiding in the core.
 
D. LARGE BREAK LOCA, due to hydrogen coming out of solution.
 
Answer B Exam Level B Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (1) 009 2.4.21 Small Break LOCA  RO Group: 2 SRO Group: 2 RO K/A 3.7 SRO K/A 4.3 Reference Title  Facility Reference Number Section Page Revision Learning Obj.
 
UFSAR    6.2.5.3 8.2.77 13 6511 Material Required for Examination Question Source: New      ,
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Question #14 Given the following conditions:
,
Plant tripped 10 minutes ago
-
Pressurizer pressure is 2100 psia and slowly increasing
-
Pressurizer level lowered to 28% and is now slowly inen asing
-
Both Steam Generator levels are 18% and slowly increasing
-
Both Steam Generator pressures are 1000 psia and steady
-
All systems are in Automatic and have actuated as required Which of the following is the correct condition for the Pressurizer heaters at this time?
(ASSUME NO OPERATOR ACTION)
A. IE heaters are off and all other heaters are on.
 
~ B. All Pressurizer heaters are on.
 
C. IE and proportional heaters are off, non IE backup heaters are on.
 
D. IE and non IE backup heaters are on, proportional heaters are off.
 
Answer A- Exam Level B Cognitive Level Application Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier:(2) ~ PPCS 010- - A4.02 Pressurizer heaters RO Group: 2 SRO Group: 2 RO K/A 3.6 SRO K/A 3.4 Reference Title Facility Reference Number Section Page Revision Learning Obj.
 
PZR Pressure and SO23-3-1.10  6 8
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Level Control .      10729
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l Material Required for Examination Question Source: Bank
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l Question #15 Given the following plant conditions:
-
Unit 2 is in MODE 3
-
  : Pressurizer Level Control System is in automatic Which of the following would cause letdown flow to increase?
.A. less of instrument air to the inservice letdown flow control valve.
 
B. 'Ihe pressurizer level transmitter equalizing valve has vibrated open.
 
C. Volume Control Tank level has increased to 85%
D. SBCS controller setpoint has failed low with 2 valves in manual permissive.
 
Answer B Exam Level B Cognitivo Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier:(2) . 011 A3.03 Charging and letdown. RO Group: 2 SRO Group: 2 RO KiA 3.2 SRO K/A 3.3 Reference Title Facility Reference Number Secton Page Revision Learning Obj.
 
PZR Pressure and SO23-3-1,10  Att. 2 18 8 Level Control      10596 Material Required for Examination Question Source: New
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Question #16 A LOCA occurred 90 minutes ago and SO23-12-3 is being implemented. You are monitoring the Floating Step for "Two-phase heat removal established."
 
Which of the following temperature sensors are required to be monitored during implementation of this floating step?
A. Hot leg RTDs.
 
B. Cold leg RTDs.
 
C. Core exit thermocouples.
 
I D. Heated junction thermocouples,    i i
i Answer C Exam Level B Cognitive Level Memory  Facility San Onofre 2 & 3 Exam Date 4/16/99
-
Tier: (1) 011 okt.01 Natural circulation and cooling, including reflux RO Group: 2 SRO Group: 1 .
I boiling.
 
RO K/A 4.1 SRO K/A 4.4 Reference Title Facility Reference Number Section l Page - Revision Learning Obj. ;
LOCA  SO23-12-3  FS-4 37 15 2537 i
i Material Required for Examination      l Question Source: NRC 6/98 J
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Question #17      i i
Given the following conditions:
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  -
A large loss of coolant accident is in progress
        ]
.
  -
SIAS, CIAS, MSIS, CSAS, and RAS have actuated    1
  -
RWSTievelis 16%-      !
  -
Emergency sump level is 20'    j
  -
ECCS valves are in the following positions.
 
-
RWST Suction valves HV9300/HV9301 OPEN    4
  -
Containment sump isolation valves HV9302/HV9303 OFEN
  -
Containment sump isolation valves HV9304/HV9305 OPEN
  -
Si pumps combined recire valves HV9306/HV9307 OPEN i
Which of the following valve (s) has failed to automatically reposition to its Recirculation  1 Actuation Signal position?      )
l A. ' HV9300!HV9301.
 
.
.
B. HV9302/HV9303.
 
C. HV9304/HV9305.
 
D. HV9306/HV9307..
        ]
Answer D Exam Level & Cognitive Level Comprehension Facility San Onotre 2 & 3 Exam Date 4/16/99 Tier: (2) 013 a2.01 LOCA  RO Group: 1 SRO Group: 1 RO K/A 4.6 SRO K/A 4.8 ReferenceTitle ' Facility Reference Number Section Page Revision Learning Obj.
 
ESFAS Operation - SO23-3-2.22  Att.15 102 12 6221 Material Required for Examination Question Source: Bank
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! Question #18 He plant is in normal operation at 100% power, when one CEA drops fully into the core.
 
Which of the following statements correctly describes the plant response to this event, assuming no operator action?
A. Reactor power decreases and RCS temperature decreases below program.  )
B. Turbine MWs lower and RCS temperature stays on program.
 
i C. Reactor power decrea.ses and RCS temperature stays on program.
 
!
D. Turbine MWs constant and RCS temperature decreases below program.
 
Answer A Exam Level B Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (2) 014 A2.03 Dropped Rod. RO Group: 2 SRO Group: 1 RO K/A 3.6 SRO K/A 4.1 Reference Title Facility Reference Number Section Page Revision Leaming Obj.
 
Misaligned CEA SO23-13-13  2 4 4362 Material Required for Examination Question Source: Bank i
 
w Question #19 A reactor startup is in progress and the reactor is approaching criticality.
 
,
Which set of parameters correctly describes the indications used to declare criticality?  !
A. Neutron count rate increasing, SUR positive, rods being withdrawn.
 
B. Neutron count rate decreasing, SUR negative, rods being inserted.
 
- C. Neutron count rate increasing, SUR positive, rod motion stopped. j D. Neutron count rate decreasing, SUR zero, rod motion stopped.
 
!
Answer ' C Exam Level B Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (2) 015 k5.05 Criticality and its indcations. RO Group: 1 SRO Group: 1 RO K/A 4.1 SRO K/A 4.4 Reference Title Facikty Reference Number Section Page Revision Learning Obj.
 
Reactor Startup SO23-3-1.1  Att. 2 31 19 4392 Material Required for Examination      i Question Source: Bank i
)
e
 
Question #20 The plant has just tripped from 100% power. What effect will a rise in containment temperature (i.e. from 80 F to 250 F) have on the Steam Generator Narrow Range level instruments?
A. Actual level will be higher than indicated level due to voiding in the variable leg.
 
B. ' Actual level will be higher than indicated level due to reference leg temperature
  ' increase.
 
~
C. Indicated level will be higher than actual level due to voiding in the variable leg.
 
D. Indicated level will be higher than actual level due to reference leg temperature increase.
 
Answer D Exam Level B Cognitive Level Comprehension Facihty San Onofre 2 & 3 Exam Date 4/16/99 Tier: ( 2) 016 2.4.48 Non-Nuclear instrumentation RO Group: 2 SRO Group: 2 System RO K/A 3.5 SRO K/A 3.8 '
Reference Title Facihty Reference Number Sechon Page Revision Learning Obj.
 
Instrumentation      -
      *49g5 Genenc Fundamentals Material Required for Examination Question Source: Bank
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I
 
I I
L        )
f        I
' Question #21 -
L Which of the following could be an indication of core uncovery?
'
(Assume instruments are accurate)      j CET Temperature equal to:
A. 555 degrees Fahrenheit with RCS Pressure equal to 1200 psia.
 
B,- ' 585 degrees Fahrenheit with RCS Pressure equal to 1350 psia.
 
C. 595 degrees Fahrenheit with RCS Pressure equal to 1500 psia.
 
D. 605 degrees Fahrenheit with RCS Pressure equal to 1650 psia.-
Answer D Exam Level B Cognitive Level Application Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (2) 017 k5.03 Indicationof Superheating. RO Group: 1 SRO Group: 1 RO KIA 3.7  SRO K/A 4.1 )
Reference Title Facility Reference Number Section Page Revision Learning Obj.
 
LOCA Bases SO2}14-3  Att.1 51 4 4059 I
Material Required for Examination      l Question Source: New
        ,
;
 
Question #22      )
Unit 2 was operating at full power when a plant trip occurred. The operators have initiated SO23-12-1, Standard Post Trip Actions.
 
Plant conditions are as follows:
-
One CEA is not fully inserted
-
Pressurizer levelis 20% and rising
-
Pressurizer pressure is 1950 psia and rising
-
S/G narrow range water levels are at 29% with MFW RTO actuated
-
Containment average temperature is 125 F
-
Containment average pressure is 1.0 psig What is the correct operator action to be taken at this time, per the SPTAs?
A. Ensure normal containment cooling is functioning properly.
 
B. Emergency borate the RCS, C. Reenergize Pzr heaters to raise pressurizer pressure.
 
D. Override AFW system to feed both S/Gs at greater than 200 gpm.
 
Answer A Exam Level B Cogndive Level Comprehension Facihty San Onotre 2 & 3 Exam Date 4/16/99 Tier: (2) 022 Generic 2.4.21 Knowledge of the parameters used to RO Group: 1 SRO Grosp: 1 asses the status of safety functions.
 
RO K/A 3.7 SRO K/A 4.3 Reference Title Facility Reference Number Secten Page Revision Learning Obj.
 
SPTA  SO23-12-1  11 15 5359 Material Required for Examination Question Source: Bank
 
- Question #23 Plant is operating in a normal full power alignment.
 
Which of the following will result in a loss of letdown flow?
A. Temperature of 150 F leaving the letdown heat exchanger.
 
B. Volume Control Tank outlet valve LV-0227B fails closed.
 
C. Loss of instrument air to FV203 Boronometer/ Rad Monitor control valve.
 
D. 80 gpm letdown flow with only one charging pump running.
 
Answer B Exam Level B Cognitive Level Comprehension - Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (1) -022- AK3.04 isolating letdown  RO Group: 2 SRO Group: 2
  .
RO K/A 3.2 SRO K/A 3.4 Reference Title Facility Reference Number Section Page Revision Learning Obj.
 
CVCS  D8D-SO23-390  FiO. D-1 160 5 8992 j Material Required for Examination Question Source: New I
i l
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I
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l
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l Question #24 Which of the following is a condition requiring emergency boration?
A. Part length CEAs inserted to 138 inches withdrawn with Unit at 90% power.
 
B. bss of all CEA Reed Switch Position indication during a reactor startup.
 
C. Regulating Group 6 CEAs inserted to 100 inches withdrawn with the Unit at 100% power.
 
D. Loss of Pulse Counter CEA Position indication.
 
Answer C Exam Level B Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (1) 024 ak3.01 When emergency boralbo is required. RO Group: 1 SRO Group: 1 RO K/A 4.1 SRO K/A 4.4 Reference Title Facility Reference Number Section Page Revision Learning Obj.
 
Emergency Boration of SO23-13-11  2 4 the RCS      6552 Material Required for Examinati.on Question Source: New
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j
 
i
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t
 
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Question #25 Given the following plant conditions:
-
HPSI Pump 2P-018 is aligned to TRAIN B
-
targe Break LOCA inside Containment has occurred on Unit 2
-
Pressurizer pressure is 900 psia    4
-
Containment pressure is 13 psig Which of the following TRAIN B pumps should be running due to ESFAS actuations?
A. LPSI Pump P-016, HPSI Pump P-019, HPSI Pump P-018.
 
B. : CS Pump P-013, HPSI Pump P-019, HPSI Pump P-018.
 
C. CS Pump P-013, LPSI Pump P-016, HPSI Pump P-019.
 
D. CS Pump P-013, LPSI Pump P-016, HPSI Pump P-018.
 
Answer D. Exam Level B Cogndive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: ( 2) 026 K2.01 Containment Spray Pumps RO Group: 2 SRO Group: 1 RO K/A 3.4 ' SRO K/A 3.6 Reference Title Facility Reference Number Section Page  Revision Learning Obj.
 
Safety injection. DBO-So21740  1.1.1.1 40.41.43  2 732g Containment Spray and  1.1.1.2 Shutdown Cooling
    "
Systems Material Required for Examination Question Source: New
.
 
        ,
n Question #26        i Which of the following Pressurizer Pressure / level parameters would require entry into a  (
Technical Specification action statement with Unit 3 at 100% power?    J A. levelof 28%.      ,
        !
B. level of 56%.
C. Pressure of 2030 psia.
 
D. Pressure of 2280 psia.
 
Answer D Exam Level B Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (1) 027 AA2.04 Technical Specification limits for RCS pressure. RO Group: 1 SRO Group: 2 l
        ' l RO K/A 3.7 SRO K/A - 4.3 !
Reference Title Facility Reference Number Section Page Revision Learning Obj.
 
I Technical Reactor Coolant System 3.4.1 3.4-1 Specifcatons -      6710 l Material Required for Examination Question Source: New
 
E Question #27        !
l l
What is the purpose of the Trisodium Phosphate (TSP) Dodecahydrate baskets in Containment?  i l
'        i
        ;
        '
i A. Minimize the evolution of Hydrogen from containment sump water.
 
l B. Minimize the evolution of Oxygen from containment sump water.
 
C. Lower pH of containment sump water.
 
D. Raise pH of containment sump water.
 
Answer D Exam Level B Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99
        *
Tier: (2) 027 kl.01 CSS  RO Group: 3 SRO Group: 2 RO K/A 3.4 SRO K/A 3.7 Reference Title  a:ility Reference Section Page Revision Learning Obj.
 
umber Safety injection, Containment Sprh, - JBD-SC23-740 1.1.1.2 43 2 and Shutdown Cooling Systems    *1285
  ,
i Material Required for Examination Question Source: New L
 
p        1 Question #28 Given the following plant conditions:      j l
-
Reactor Trip has just occurred    )
-
Pressurizer levelis 19% and rising
-
Pressurizer pressure is 1950 psia and lowering Which of the following actions is required per SO23-12-1, Standard Post Trip Actions, for these conditions?
A. Verify all available charging and HPSI Pumps are running.
 
B. Ensure all available charging pumps are running. f l
C. Verify all pressurizer heaters are ON. i D. Ensure Pressurizer normal and auxiliary spray valves closed.  ;
a Answer D Exam Level B Cognitive Level Memory Facility San Onotre 2 & 3 Exam Date 4/16/99 l Tier:(1) 028 ak305 Actions contained in EOP for Pzr level RO Group: 3 SRO Group: 3 ,
malfunction.      l RO K/A 3.7 SRO K/A 3.7 Reference Title Facility Reference Number Section Page Revision Learning Obj.
 
SPTA  SO23-12-1  5 15 622 Material Required for Examination Question Source: Bank
 
I Question #29 Given the following plant conditions:
  -
An inadvertent MSIS has occurred
  -
The Reactor trip circuit breakers have HQIopened
  -
The Anticipated Transient Without SCRAM / Diverse SCRAM System (ATWS/ DSS) has caused a reactor trip i
Which of the following has automatically occurred to mitigate the event?
A. SIAS is initiated.
 
B. CEDMCS MG set output BREAKERS open.
 
l C. ' CEDMCS MG set output CONTACTORS open.
 
l D. 480V Buses B15 and B16 deenergized. J
        \
Answer C Exam Level B Cognitive Level Memory Facility San Onotre 2 & 3 Exam Date 4/16/99 I Tier; (1) 029 ek3.01 Verifying a reactor trip; methods RO Group: 2 SRO Group: 1 j
    '
l RO K/A 4.2 SR O K/A 4.5
        '
Reference Title Facility Reference Number Section Page Revision Learning Obj.
 
*
Plant Protection DBD-SO23-710  2.2.4 107 2 733g System        l Material Required for Examination
- Question Source: New
 
,
  .
Question #30 Given the following plant conditions:
I
-
Unit 2 tripped 25 minutes ago
-
A Steam Generater Tube Rupture has been diagnosed and RCS cooldown has
        '
been initiated
-
Hot leg temperature is 529'F
- . RCPs 2P001 and 2P004 have been secured
-
S/G levels are 27% in E089 and 31% in E08fs and slowly rising
-
Pressurizer level is 20% and slowly rising
-
Pressurizer pressure is 1480 psia-l Which of the following actions should be performed at this time?
A. Perform HPSI throttle stop.
 
B. Override and feed both steam generators.
 
C. Secure 2 charging pumps. l D. Isolate the affected steam generator.
 
Answer D Exam Level B Cognitive Level Application Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: ( 2) 035 A2.01 Faulted or ruptured S/Gs RO Group: 2 SRO Group: 2 l
RO K/A 4.5 SRO K/A 4.6 Reference Title Facility Reference Number Section Page Revision Learning Obj.
 
SGTR  SO23-12-4  11 16 6g74 Material Required for Examination      )
Question Source: New      I
 
g i
Question #31 Given the following plant conditions:
-
Unit 2 tripped 18 minutes ago    ,
-
Steam Generator Tube Rupture has been diagnosed and SO23-12-4 has been implemented
-
All Reactor Coolant Pumps were secured 12 minutes ago
-
Natural Circulation Criteria has been verified
-
HPSI throttle /stop has been completed; all HPSI and charging pumps are secured
-
Pressurizer pressure is 1150 psia AND slowly lowering
-
Pressurizer level is 66% MD slowly rising Which of the following conditions would explain the pressurizer level response?
A. Pressurizer level instrument variable leg has broken.
 
B. Voiding is occurring in the RCS head region.
 
C. S/G back leakage into the RCS.
 
D. . RCS heatup is occurring.
 
Answer B Exam Level B Cognitive Level Comprehension Facihty San Onofre 2 & 3 Exam Date 4/16/99 Tier:(1) 038 ekt.03 Natural Circulation  RO Group: 2 SRO Group: 2 RO K/A 3.9 SRO K/A 4.2 Reference Title . Facility Reference Number Section Page Revision Learning Obj.
 
SGTR Bases  $023-14-4  Att,1 $2 3 4140
. Material Required for Examination
. Question Source: New
        .
 
Question #32 -
Unit 3 is at 17% power and the operator has just applied Block 1. cad when a gener9 tor trip occurs.
 
Describe the expected response of the Main Steam Safety Valves (MSSVs) and the Steam Bypass Control System (SBCS) to this event.    '
A. MSSVs will initially open, then rescat; SBCS valves will open as required to control main steam pressure.
 
B. MSSVs will not open; SBCS valves will open as required to control main steam
         '
         '
pressure.
operator and senior reactor operator license applications (Office of Management and Budget (OMB) approval number 3150-0090), medical certifications (OMB approval number 3150-0024),
 
and waiver requests (if any) (OMB approval number 3150-0090) at least 30 days before the first examination date. If the applications are not received at least 30 days before the examination l
l C. MSSVs will initially open, then rescat; SBCS valves receive a " quick-open" block l signal due to low Tave.
i date, a postponement may be necessary. Signed applications certifying that all training has been completed should be submitted at least 14 days before the first examination date.
 
D. MSSVs and SBCS valves will be unaffected.
 
Answer B Exam Level B Cognitive Level Comprehension Facihty San Onofre 2 8 3 Exam Date 4/16/99 Tier:(2) 041 k4.t 7 Reactor Trip  RO Group: 3 SRO Group: 3 RO K/A 3.7 SRO K/A 3.7 Reference Title Facility Reference Number Section Page Revision Learning Obj.
 
S/G and Secondary DDD-SO23-:x.,5 6.2.5 133 1 Side      6455 Material Required for Examination Question Source: New
 
m- -
Question #33 While performing a heat treat on Unit 3, the condenser low vacuum alarm is received. You note that main condenser backpressure is 5.8" Hg abs.    !
What effect should this have on Steam Bypass Control System (SBCS) operation?
A. SBCS is disabled due to low condenser vacuum.
 
' B. The SBCS " Emergency Off' push button should be pushed to prevent system operation during the low vacuum condition.
 
C. Vacut m is not degraded enough to have an effect or require any actions.
 
,
D. SBCS " quick-open" actuation is blocked but modulate operation is still enaHed. i Answer C Exam Level Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (1) 0S1 ak3.01- Loss of steam dump capability upon loss of RO Group: 1 SRO Group: 1 .
condenser vacuum.
 
RO K/A 2.8 SRO K!A 3.1 Reference Title Facilvy Reference Number Section Page Revision Learning Obj.
 
Steam Bypass System SO23-3 2,18  3.0 3 12 Operation      6455
. Material Required for Examination Question Source: New
 
[
l l-Question #34
.
Given the following plant conditions:
  -
Unit 2 tripped 45 minutes ago
  -
An Excess Steam Demand Event is in progress
  -
E089 is about to reach dryout Which of the following conditions could occur if steaming is not commenced on the unaffected S/G?
A. Loss'of natural circulation in the affected RCS loop resulting in stabilization of RCS temperatures.
 
B. less of RCS subcooling resulting in a loss of natural circulation in both RCS loops.
 
C. loss of inventory in the affected S/G resuhing in a loss of natural circulation in
        *
that loop.
 
D. Loss of natural circulation in both RCS loops resulting in RCS repressurization.
 
Answer D Exam Level B Cogndive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (1) - 054 ak3.04 Actions contained in EOP's for loss of MFW. RO Group: 2 SRO Group: 2 RO K/A 4.4 SRO K/A 4.6 Reference Title Facility Reference Number Section Page Revision Learning Obj.
 
ESDE Bases SO2314-5  Att.1 21 4 6805 Material Required for Examination Question Source: New
 
l
 
rv    ,
'
I l
l Question #35        3
        !
l Plant conditions are as follows:
    '
\;        1
  -
A loss of Offsite Power caused a reactor trip 30 minutes ago
  -
MSIVs have been manually closed
,
  -
Main Steam pressure is being maintained at 1000 psia following the reactor trip Which of the following conditions would be expected for the above conditions?
A. Hot leg temperature of 550 F and rising.
 
Cold leg temperature of 530*F and lowering.
 
B. Hot leg temperature of 570 F and lowering.    !
Cold leg temperature stable at 545 F. i C. Hot leg temperature of 587 F and rising.
 
Cold leg temperature stable at 545 F.


.
.
D. Hot leg temperature of 570 F and lowering.
9901210109 990113 l PDR ADOCK 05000361 y PDR l
 
Cold leg temperature of 540 F and lowering.
 
Answer 0 Exam Level B Cognitive Level ' Comprehension Facility San Onofre 2 & 3 Exam Date'4/16/99 Tier: (1) 055- akt.02 Natural Circulatioin Cooling RO Group: 1 SRO Group: 1 RO K/A 4.1 SRO K/A 4.4 Reference Title Facility Reference Number Section Page Revision Learnin0 Obj.
 
Loss of Offsite Power SO23-12-7  8 15 gg
        ,
Material Required for Examination Question Source: New-
  ,
        $
 
r Question #36 De plant was initially operating at 100% power.
 
A complete Loss of Offsite Power occurred 5 minutes ago. N.Q operator actions have been taken and all systems functioned as designed.
 
How are the S/Gs maintaining RCS heat removal?
A. AFW supplying S/Gs; steaming out Main Steam Safety Valves.


B. AFW supplying S/Gs; steaming using the Atmosoheric Dump Valves.
C. MFW supplying S/Gs; no steaming required.
D. MFW supplying S/Gs; steaming using the SBCS.
i A.iswer A Exam Level B CognitiveLevel Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (1) 058 AA2.56 RCS T-ave. RO Group: 3 SRO Group: 3 RO K/A 3.6 SRO K/A 3.7 Reference Title Facility Reference Number Section Page Revision Learning Obj. )
SPTA  SO23-12-1  8 15 6gg6 Material Required for Examination Question Source: Bank
        !
        !
I l
  ._.
r p-
Question #37'        j Given the following plant conditions:
  -- Channel"A" RCS hot leg temperature TT-0122-1 has failed and the affected  !
functional unitt have been bypassed    ;
  -
Channel "C" RCS hot leg temperature TF-0122-3 has also failed and the affected functiorial units have been placed in trip
  -
A loss of vital bus inverter 2Y004 occurs and the Reactor does NO.I trip  4
  -
All other plant conditions are normal i
Which of the following action is required?
I A. Vital bus 2YO4 must be placed on its alternate source within 24 hours. j B. Manually trip the reactor.
C. Initiate a Rapid Downpower per SO23-5-1.7, Power Operations.
D. Initiate a normal plant shutdown per SO23-5-1.7, Power Operations. I
        !
Answer C Exam Level B Cognitive Level Comprehension Facility San Onotre 2 & 3 Exam Date 4/16/99 Tier: (1) 057 aa2.03 RPS panel alarm annuncetors and RO Group: 1 SRO Group: 1 l trip indicators RO K/A 3.7 SRO K/A 3.9
        ]
Reference Title Facility Reference Number Section Page Revision Learning Obj. j RPS/ Loss of Vital Bus SO23-13-18  Att 2 12 2 6593~
Invertar Material Required for Examination Question Source: New
  .
  .
__ _m.


w - -
l San Onofre Nuclear Generating Station -4-   l E-Mail report to T. Frye (TJF)
Question #38 Given the following plant conditions:
E-Mail report to D. Lange (DJL)
  -
E-Mail report to NRR Event Tracking System (IPAS)
Unit 2 tripped 40 minutes ago
E-Mail report to Document Control Desk (DOCDESK)
  -
   /
Both Main Steam isolation Valves (MSIVs) have failed closed
bec to DCD (IE01) - DRS, DRP, and Decommissioning d
  -
bec distrib. by RIV:
All Auxiliary Feedwater has been lost and could not be restored Which of the following methods should be used to recover the RCS Heat Removal Safety Function?
Regional Administrator DRS Director    -
A.' Establish IIPSI flow to the cold legs for once-through core cooling.
Resident inspector DRP Director DRS-PSB DRS Director MIS System
 
'
B .- Reestablish Main Feedwater flow to the S/Gs.
Branch Chief (DRP/E)
 
RIV File Senior Project inspector (DRP/E)
C. Establish LPSI flow to the cold legs for once-through core cooling.
Branch Chief (DRP/TSS)
 
DOCUMENT NAME: R:\_SO23\SO930111.]lp To receive copy of document, Indicate in box: "C' = Copy without enclosures *E' = Copy with enclosures "N* = No copy l ' C:OB  l@- D:DRP l  l  l  l JLPellet/imb6 " '
D. Establish low pressure alternate feedwater flow using condensate pumps.
KEBrockmanW 01/fV99  01/tV99 OFFICIAL RECORD COPY    ,
 
Answer D Exam Level B Cognitive Level Application Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (2) 059 k304 RCS   RO Group: 1 SRO Group: 1 RO K/A 3.6 SRO K/A 3.8 Reference Title Facility Reference Number Secton Page Revision Learning Obj.
 
Functional Recovery SO23-12-9  Art. 8 330 18 69)6 ,
Material Required for Examination      I Question Source: Bank
        :
)
 
,
. Question #39 Given the following plant conditions:
  -
  ' Unit 2 is at 355'F.-
  --
A cooldown is in progress using the S/G's Which of the following is required to be OPERABLE per Technical Specification 3.7.5, Auxiliary Feedwater System?.
A. 'All three AFW Pumps.
 
B. Two motor driven AFW Pumps.
 
C. One motor driven and one steam driven AFW Pump.
 
D. One motor driven AFW Pump.
 
Answer A Exam Level B Cognitive Leve Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (2) 061 Generic 2.1.12 Ability to apply Technical SpecifK:ations to a RO Group: 1 SRO Group: 1 System '
RO K/A 2.9 SRO K/A 4.0 Reference Title Facility Reference Number Section Page Revision Leaming Obj.
 
Technical  Auxiliary Feedwater System 3.7.5 3.7-11 Specifications 6642
         ,
         ,
Material. Required for Examination l
   *
.. Question Source: New      l
 
I
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l l
 
+
~,
 
i.
 
.-
Question #40      :
Given the following information:
  -. The unit tripped fmm 100% power 20 minutes ago
  --
Both Steam Generator levels lowered to 17% NR and recovered to 26% NR
  -
The operator has depressed the " Override" pushbuttons for the AFW valves and is feeding each steam generator at 450 gpm Subsequently:
  -
Steam Generator E088 pressure decreases to 700 psia with level at 25% NR.
 
-
Steam Generator E089 pressure decreases to 850 psia.with level at 27% NR Which of the following describes the status of tile AFW system (assume no other operator actions have occurred)?
        .
A. Both steam generator E088 and E089 are being fed.
 
B. E088 is being fed and E089 is isolated.
 
C. Neither steam generator E088 nor E089 is being fed.
 
D. E089 is being fed and E088 is isol.ited.
 
Answer A Exam Level B Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (2) 061 a3.04 Automatic AFW isolation  RO Group: 1 SRO Group: 1 RO K/A 4.1 SRO K/A 4.2 Reference Title Facility Reference Number Section Page Revision Learning Obj.
 
Plant Protection DBD-SO23-710  2.1.2.7 99 2 System 4726 T
Material Required for Examination -
Question Source: Bank
 
m i
i Question #41 i'
f Given the following:
      '
-
Both Units 2 and 3 are at full power
        !'
- .
Unit 2 is preparing to shift Train A SWC pumps-
-
The operator assigned to perform 4KV breaker manipulations goes to the wrong unit and tums off DC control power to 3P112, which was running at the time What effect does this have on the Unit 3 SWC system?
i A. SWC pump 3P112 breaker opens, SWC pump low flow alarms are received. j B. SWC pump 3P112 breaker opens, no alarms are received due to the loss of control power.
 
C. SWC pump 3P112 breaker stays closed, no remote operation or automatic l
tripping is available.
 
D. SWC pump 3P1 i2 breaker stays closed, no remote operation is possible but
  = automatic trips are functional.
 
Answer C Exam Level B Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 }
Tier: ( 2) 063 K3.02 Components using DC control RO Group: 2  SRO Group: 1 Power RO K/A 3.5 SRO K/A 3.7 Reference Title Facility Reference Number Section Page Revision Learning Obj.
 
Elementary Diagram 30795   18 5220 Material Required for Examination Question Source: New l
 
I i.
 
, Question #42 l
Plant conditions are as follows:
l
  -
Unit 2 tripped 10 minutes ago on low pressurizer pressure
  -
A loss of offsite power occurred 6 minutes ago
  -
Pressurizer pressure is now I430 psia    )
  -
Bus 2A04 is energized      j
  --
20003 has just tripped and bus 2A06 is deenergized Which of the following diesel generator trips could have caused the loss of 20003?
A.' High crankcase pressure,    i l
B. liigh jacket water cooling temperature.
 
C. bss of excitation.
 
D. Generator differential.      I l
Answer D Exam Level B Cognitive Level Comprehension Facihty San Onofre 2 & 3 Exam Date 4/16/99 Tier: (2) 064 k4.02  Trips for ED/G wNie RO Group: 2 SRO Group: 2 operating (normal or emergency) RO K/A 3.9 SRO K/A 4.2 Reference Title - Facility Reference Number Secton Page Revi'Jon Ler.rning Obj.
 
Elementary Diagram 30330    22 - 5345
        !
Material Required for Examination Question Source: New      l l
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-
l Question #43 Given the following plant conditions:
  -
Plant is operating at 100% power
  -
Alarm 61 A15 (Fire Detected) is received in the Control Room
  -
The Fire Computer indicates the fire is in the Unit 2 computer room  ;
Which of the following explains the expected conditions for a fire in the computer room?
A. Supply and exhaust dampers open, for 'once through' air flow.
 
B. Supply and exhaust dampers close, isolating the computer room.
 
C. Supply damper closes, exhaust damper opens to exhaust smoke.
 
D. Supply damper opens, exhaust damper closes to allow fresh air in.
 
Answer B Exam Level B Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (1) 067 aat.05 Plant and Control Room Ventilation System RO Group: 1 SRO Group: 1 RO K/A 3.0 SRO K/A 3.1 Reference Title Facility Reference Number Section Page Revision Learning Obj. .
Halon Fire Protection SO23-7-4  6.3.5 5 2 System Operation      8356 Material Required for Examination Question Source: New
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0
 
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1
 
j
 
r
. Question #44 A release of one of the Radwaste Secondary Tanks is in progress. Liquid Rad Waste Monitor (RE-7813) fails low.
 
Which of the following will allow the release to recommence?
A. .'Ihe Plant Superintendent must approve the release permit.
 
B. Two independent samples, release rate calculations, and valve lineup verifications must be performed.
 
C. We sample flowrate must be estimated at least once every 4 hours.
 
D. The liquid release cannot recommence until RE-7813 is determined to be OPERABLE.
 
Answer B Exam Level B Cognitive Level Memory Facility San Onoire 2 & 3 Exam Date 4/16/99 Tier: (2) 068 k6.10 Radiation monitors  RO Group: 1 SRO Group: 1 RO K/A 2.5 SRO K/A 2.9 Reference Title Facility Reference Number Section Page Revision Learning Obj.
 
Liquid Radioactive SO23-8-7  Att. 6 95 10 Waste Release 9068 Operations Material Required for Examination Question Source: New      j
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Question #45 l
Given the following:      j
  -
  ' Wide Range Gas Monitor (WRGM),3RE-7865, is aligned to the Plant Vent  )
Stack
  -
A Waste Gas Decay Tank release is in progress    !
  -
Alarm 61 A27," Plant Vent Stack Radiation Hi",is received due to high radiation on 3RE-7865
        \
        '
Which of the following best describes the automatic action (s) caused by the WRGM for the above set of conditions?      l A. The monitor realigns to containment purge to sample that flow path.
 
- B. Sample flow control shifts from Isokinetic flow control to manual flow control.
 
C. The waste gas discharge flow control valve FV-7202 closes.
 
D. The outside containment mini-purge isolation valve HV9825 closes.
 
Answer C Exam Level B Cognitive Level Memory Facihty San Onofre 2 & 3 Exam Date 4/16/99 Tier: (2) 071 k4.04 isolation of waste gas release tanks RO Group: 1 SRO Group: 1~
RO K/A 2.9 SRO K/A 3.4 '
Reference Title Fact:.ty Reference Number Section Page Revision Learning Obj.
 
Radwaste Gas SO23-8-15  4.4 - 3 11 Discharge      9413 Material Required for Examination Question Source: NRC 6/98 l
 
p
 
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!.        l Question #46 i
l' Unit 2 is in MODE 6.- During fuel inspection activities, the fuel inspection device was raised out  <
l of the Spent Fuel Pool.      )
Airbome radiation levels as sensed'by the Fuel Handling Building Vent Airbome Monitors RE-7822 & RE-7823 have exceeded the alarm / trip setpoint.
)
-
RE-7822 is in bypass
- RE-7823 is in normal operation Based on these conditions, which of the following statements represents correct system response?
A. FHIS actuation, Train 'A'.
B. FHIS actuation, Train 'B'. l l
C. FHIS actuation, Trains 'A' and 'B'.
        !
D. No FHIS actuation occurs. i Answer B Exam Level B Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (2) 072 kl.03 Fuel Building isolation  RO Group: 1  SRO Group: 1 RO K/A 3.6 SRO K/A 3.7 Reference Title  Facility Reference Section Page Revision Learning Obj.
Number Fuel Handling Area Vent airborne Process SO23-3-2.24.5 6.1.4 3 6 6302 Radiation Monitoring System Operaton Material Required for Examination Question Source: Bank
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Question #47 '
Given the following plant conditions:
  -
A Waste Gas Decay Tank release using 2/3 RT-7808. Plant Vent Stack Airbome Radiation Monitor, is in progress.
-
Rad monitor 3RT-7865, Containment / Plant Vent Stack Radiation Monitor, becomes INOPERABLE.
What additional action must be performed to allow the release to continue?
        :
A. Process flow rate must be estimated at least once every 12 hours.
B. Two independent samples must be drawn at least once every 4 hours.
C. Reverify valve alignment, sample and recalculate release rate calculations.
D. Verify composite samplers are operational for the gaseous radwaste system.
Answer A Exam Level 8 Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (2) 073 Generic 2.1.20 Ability to execute procedure steps. RO Group: 2 SRO Group: 2 RO K/A 4.3  SRO K/A 4.2 Reference Title Facihty Reference Number Section Page Revision Learning Obj.
Radwaste Gas so23-815  4.11 4 Discharge      10103 Material Required for Examination Question Source: New
l Question #48 he plant has just tripped from 100% power operation, the SPTAs are being carried out and plant conditions are as follows:
- All CEAs are fully inserted    !
-
PZR level is 20%      l
-
RCS Subcooling is 88 F
-
Pressurizer pressure is 1410 psia
-
RCS cold leg temperature is 490 F
-
CNTMT pressure is 0.5 psig
-
All ESFAS Systems have actuated as required l
l Which of the following is required per the SPTAs for Reactor Coolant Pump operation?  i I
A. Trip four RCPs.
B. Trip two RCPs.
l C. Leave all four RCPs mnning.
D. Trip one RCP.      l l
        !
Answer B Exam Level B Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 Thr: (1) 074 ek304 Tripping RCPs  RO Group: 1 SRO Group: 1 RO K/A 3.9 SRO K/A 4.2 Reference Title Facihty Reference Number Section Page Revision teamirq Obj.
SPTA  SO23-12-1  5 15 1622 Material Required for Examination Question Source: New I
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D Question #49      l
        ,
Which of the following electrical buses supply power to the 4 Saltwater Cooling Pumps located in the Unit 2 Saltwater Cooling Pump Room?
A. One (1) pump from each of 2B04,3B04,2B06, and 3B06.
B. ' Two (2) pumps from each of 2B04 and '2B06.    ,
l C. One (1) pump from each of 2A04,3A04,2A06, and 3A06. J
' D. Two (2) pumps from each of 2A04 and 2A06. l Answer C Exam t.evel B f Cognitive Level - Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (2) 075 K2.03 Cire Water System Emergency RO Group: 2 SRO Group: 2 Essential SWS pumps RO K/A 2.6  SRO K/A 2.7 Reference Title Facility Reference Number Section Page Revision Learning Obj.
Saltwate' Cooling DBD-SO23-410  Table C-1 98 2 System 6727
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Material Required for Examination Question Source: New l
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i Question #50 l
     ^'^
l A fire has been detected in Containment. As the Fire Brigade Technical Advisor working with the l Fire Department, you are asked what type of automatic water suppression system is used in the immediate vicinity of RCP P001.
u
 
  .)
Which of the following is the correct response?
A. A deluge water spray sprinkler.
 
I
        '
B .' A wet pipe sprinkler.
 
C. Automatic pre-action sprinkler.
 
D. No suppression system is located in the area.
 
Answer A l Exam Level B Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (2) 086 K5.03 Effect of H,0 spray on electricalcomponents RO Group: 2 SRO Group: 2 RO K/A 3.1 SRO K/A 3.4 Reference Title  Facility Reference Section Page Revision Learning Obj.
 
Number Fire Suppression Water System SO23-7-1  Att. 7 53 18 93g6 l Operation Material Required for Examination Question Source: Bank
 
- Question #51 i
With Unit 2 in MODE 1, an inadvertent CIAS occurs.
 
Which of the following describes the FIRST actions required to be performed per the AOl?
A. Initiate SO23-13-7, Loss of CCW/SWC.
 
B. Trip the Reactor Coolant purnps.-
C. Trip the Reactor and Turbine.
 
D. Override /Open CCW NCL isolation valves.
 
Answer C Exam level B Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (2) 103 a3 01 Containment isolation  RO Group 3  SRO Group: 2 RO K/A 3.9 SRO K/A 4.2 Reference Ti%  Facility Reference Section Page Revision Learning Obj.
 
Number Recovery From inadvertent Safety 3023-13-17 3.1.1 2 2 injecton/ containment isolaton 6584 Material Required for Examination Question Source: Bank l
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Question #52 The unit is operating at 100% power. The following conditions exist on Reactor Coolant Pump P002:
-
Vapor Seal Cavity Pressure  78 psig
-
Upper Seal Cavity Pressure 2240 psig
-
Middle Seal Cavity Pressure 2250 psig Which of the following actions are required for the stated conditions?
A. Full power operations may continue, trend P002 parameters.
 
B. ' Initiate a normal phmt shutddwn.
 
C. Initiate a Rapid Downpower.
 
D. Immediately trip the reactor and 5 seconds after the CEAs are inserted, trip RCP P002.
 
Answer B Exam Level 8 Cognitive Level Application Facihty San Onofre 2 & 3 Exam Date 4/16/99 Tier; (1) ' 015/17 aa2.01 Cause of RCP failure RO Group: 1 SRO Group: 1 RO K/A 3.0 SRO K/A 3.5 Reference Title Facihty Reference Number Section Page- Revision Learning Obj.
 
RCP Seal Failure SO23-13-6 3.3 3 2 6516 Material Required for Examination Question Source: Bank
 
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Question #53        )
During normal plant operations, while performing actions outside of the Control Room, what is  l the relationship between the Control Room Operators and the PEO?
A. The PEO will take direction from the CRS, but is responsible to the CO.  )
l B. He ACO will direct the PEO's activities, but will inform the CRS before action is  j taken.      j
 
i C.' De CO will direct the PEO's activities, but only with SM concurrence. j f
D. The CO will direct the PEO's activities under the supervision of the CRS. I
 
    .
Answer D Exam Level B Cognitive Level Memory Facility San Onofre 2 & 3 Exam Data 4/16/99 Tier: 2.1.1 Knowledge of conduct of operr.tions requirements RO Group:  SRO Group: ;
RO K/A 3.7 SRO K/A 3M Reference Title F.acility Reference Number Section Page Revision Learnira Obj.
 
Cor' duct of Operations SO23-0-46  6.16.5 18 a 10417 Material Required for Examination Question Source: NRC 11/98
 
ll l
 
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Question #54        i Given the following plant conditions on Unit 2:
-
RCS average temperature is 295 F.
 
--
  ' Maintenance is being conducted in the switchyard.
 
-
At 9:00 am the switchyard foreman reports a crane operator lost control and tripped open the Unit 2 switchyard Reserve Auxiliary Transformer breakers.
 
-
Substation personnel on the scene have conducted a visual inspection and report
  . that the breakers will be OPERABLE at 10:30 am.
 
.What actions are required by Technical Specifications?
A. No further action is required since the LCO will be met within the Required Action Completion Time.
 
B. Within I hour, perform surveillance test on both DGs.
 
C. Take action to suspend any positive reactivity additions until the second offsite circuit is energized.
 
D. Within i hour, verify correct breaker and power availability for the offsite circuit that was not dcenergized.
 
Answer D Exam Level B Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: 2.1.11 Knowledge of <1 hr Tech Spec action statements. RO Group:  SRO Group:
RO K/A 3.0 SRO K/A 3.8 Reference Title Facility Refererr,e Number Section Page Revision Leaming Obj.
 
Technical  Electric Power Systems 3.8.1 3.8-1 Specifications 9964 i
Material Required for Examination Question Source: NRC 6/98
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Question #55        !
    -
I Which of the following sets of conditions will allow a start (breaker closure) of Circulating Water Pump Pt 15 (Assume 2A0308 breaker racked in with DC on)?
  -
2HV5288 - CW P115 Discharge Valve
  -
2HV5100 - TPCW supply valve from Pt 15 to TPCW HX A. 2HV5288 open,2HV5100 closed.
 
B. 2HV5288 open,2HV5100 open, C. 2HV5288 closed,2HV5100 open. i l
l D. 2HV5288 closed,2HV5100 closed. i Answer A Exam Level B Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: 2.1.24 Ability to obtain and interpret electrical and mechantal RO Group:  SRO Group:
drawings.
 
RO K/A 2.8 SRO K/A 3.1 Reference Title Facihty Reference Number Section Page Revison Learning Obj.
 
Elementary oiagrams 31001,31005,31009,  17,9,4.8 4862 31061      j i
Material Required for Examination  prints: 31001,31005,31009,31061 Question Source: Bank i
m_______
 
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        '
Question #56 When observing a Motor Operated Valve (MOV) during stroke testing, it is important to stand  )
l clear of the handwheel plane.      I This is because the handwheel will rotate at high speed and could disintegrate if:
A. He limit switch fails to actuate. I B. He clutch does not disengage.
 
C. The motor phase rotation is incorrect.
 
!
D. The torque switch fails to actuate. I Answer B Exam Level B Cognitive Level Mernory Facility San Onotre 2 a 3 Exam Dtte 4/1f.99 ,
 
Tier: 2 2.12 Knowledge of Surveillance Procedure RO Group:  SRO Group:
RO K/A 3.0 SRO K/A 3.4 Reference Title Facihty Reference Number Section Page Revision Learning Obj.
 
Valve Operation SO23-O-23.1  4.13 5 5 6362 i
Material Required for Examiriation Question Source: Bank
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San Onofre Nuclear Generating Station -2-    !
l
This letter contains information collections that are subject to t' e oapenvork Reduction Act of 1995(44 U.S.C. 3501 et seq.). These information collections v ro approved by the Office of Management and Budget, approval number 3150-0101, which apires on April 30,2000. l The public reporting burden for this collection of information iu a stiraated 'o average 500 hours per response, including the time for reviewing instructions, gttherilj ar.d maintaining the data needed, writing the examinations, and completing and reviewinl1 ti e collection of in'ormation.
        .
 
_
_        ,
 
I
' Question #57
      -  _
Which of the following Reactor Protection System (RPS) Trips is NQI required by Technical
}.
Specifications?
A. Pressurizer Pressure-lmw.
 
B. Pressurir.cr Pressure-High.
 
C. Steam Generator Level-low.
 
D. Steam Generator Level-High.


,
Send comments on any aspect of this collection of information, oc i hg suggestions for reducing the burden, to the information and Records Managemen' Branch E-6 F33), U.S.
Answer D Exam L wei B Cognitive Level Memory  Facility Tsan Onofre 2 & 3 Exam Date 4/16/99 Tier: 2.222 Knowledge of limiting conditions for operatons and safety RO Group:  SRO Group: 4 limits.      l l
RO K/A 3.4 SRO K/A 4.1 Reference Title Facility Reference Number Section Page  Revision Learning Obj.


Technical RPS Instrumentation 3.3.1 Table 3.3.1-1 Specifications 7270 Material Required for Examination Question Source: Bank
Nuclear Regulatory Commission, Washington, DC 20555-0001, or isy !nte'ne; ?lectronic mail at BJS1 @NRC. GOV; and to the Desk Officer, Office of Information and Regulatory Affairs, !
        .
NEOB-10202, (3150-0101), Office of Management and Budget, Washington, DC 20503.


o I
The NRC may not conduct or sponsor, and a person is not required to respond to, a collection I of information unless it displays a currently valid OMB control number.
l Question #58 i
I Why must a MODE 6 EDMR be issued if the Spent Fuel Pool boron concentration drops below  l 2600 ppm?      !


A. The SFP water could dilute the refueling cavity when the fuel transfer tube is opened.
l Thank you for your cooperation in this matter. Mr. Rauch has been advised of the policies and guidelines referenced in this letter. If you have any questions regarding the i 1C's examination
 
, procedures and guidelines, please contact me.
'
B. The addition of spent fuel assemblies to the spent fuel pool could cause spent fuel pool criticality.
 
C. The RCS water could dilute the Spent Fuel Pool when the fuel transfer tube is )
        '
opened.
 
D. The movement of a fuel assembly out of a high density fuel rack could cause spent fuel pool criticality.
 
Answer A Exam Level B Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: 2.2.27 Knowledge of the refueling process. RO Group:  SAO Group: j RO K/A 2.6 SRO K/A 3.7 Reference fitle Facihty Reference Number Secton Page Revision Learning Obj.
 
LOCAR and EDMR ' SO123-0-13  6.2.2 10 6 4582 Material Required for Examination Question Source: Bank
 
-
_ Question #59 A worker has been assigned the task of unbolting incore detector flanges.
 
The following is the year to date dose for this worker.
 
-
Deep Dose Equivalent - 0.5 REM
-
Committed Effective Dose Equivalent - 0.2 REM Dose Rate for this task is 0.9 R/HR gamma radiation Which of the following is the maximum stay time for this worker per SONG's Administrative Limits?
      .
A. 20 minutes.
 
B. 33 minutes.
 
'
C. 53 minutes.
 
D. 66 minutes.


Sincerely, cLM*
John L. Pellet, Chief
"
Operations Branch  l Division of Reactor Safety Docket Nos.: 50-361;50-362
.
.
Answer A Exam Level B Cognitive Level Appheaton Facility San Onotre 2 & 3 Exam Date 4/16/99 Tiar: 2.3.1 Knowledge of 10 CFR:20 and related facihty radiation RO Group:  SRO Group:
License Nos.: NPF-10; NPF-15 cc:
control requirements.
 
RO K/A 2.6 SRO K/A 3.0 Reference Title Facihty Reference Number Section Page Revision Learning Obj.
 
Health Physics SO123-Vil-20  6.4.1.4 20 5  96gj Program        ]
i i
l Material Required for Examination      '
Question Source: New
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I Question #60      j
        -
 
Which of the following statements describes the relationship between dose rate and distance for a l point source?
A. The dose rate varies inversely to the square of the distance.
 
l B. The dose rate varies inversely to distance.
 
C. The dose rate does not drop off appreciably with distance.
 
!
D. The dose rate is insignificant at a distance of three feet.
 
Answer A Exam Level 8 Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: 2.3.2 Knowledge of facihty ALARA program. RO Group:  SRO Group:
RO K/A 2.5 SRO K/A 2.9 j Reference Title Facility Reference Number Secton Page Revision Learning Obj.
 
Generic Fundamentals    96g}
l Material Required for Examination Question Source: Bank i
 
r Question #61        l Given the following:
-
The unit is in MODE 1
  -. 2RT-7865 is aligned to the Plant Vent Stack
  -
Containment Mini-Purge is in progress Which of the following would require immediate securing of the Containment Mini-Purge?
A. 2RT-7865, Containment / Plant Vent Stack Radiation Monitor becomes INOPERABLE.
 
B. 2RT-7804, Contamment Airborne Radiation Monitor becomes INOPERABLE.
 
C. 2RT-7828, Containment Purge Stack Radiation Monitor becomes INOPERABLE.
 
D. 2FR-7826, Containment Purge Stack Process Flow Recorder becomes INOPERABLE.
 
Answer C Exam Level Cognitive Level Comprehension Facility San Onotre 2 & 3 Exam Date 4/16/99 Tier: 2.3.9 Knowledge of the process for performing a containment RO Group:  SRO Group:
purge.
 
R O K/A 2.5 SRO K/A 3.4 Reference Title  Facility Reference Number Section Page Revision Leaming Obj.
 
Containment Purge and  SO23-1-4.2  Att.13 70 22 Recirculation Filtration System -
7576 Material Required for Examination Question Source: Bank i
 
f I
l l Question #62
!
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l A major earthquake occurred ten minutes ago. The Reactor has tripped and the following l
'
conditions exist on Unit 2:      j
        )
-
A loss of the switchyard has occurred
-
Both S/Gs are at 17% NR level and no AFW flow can be established to either S/G
-
Pressurizer level is 12% and decreasing    i
-
Main Steam Line Radiation Monitors are trending upscale  )
i Which of the following is the appropriate Emergency Operating Instruction to mitigate the Unit 2 event?
I A. SO23-12-4, Steam Generator Tube Rupture.
 
B. SO23-12-6, Loss of Feedwater. j C. SO23-12-7, Loss of Forced Circulation / loss of Offsite Power.
 
D. SO23-12-9, Functional Recovery. l Answer D Exam Level B Cognitive Level Apphcation Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: 2.4.1 Knowledge of EOP entry conditions and immediate achon RO Group:  SRO Group:
steps.
 
RO K/A 4.3 SRO K/A 4.6 Reference Title Facihty Reference Number Section Page Revision Learning Obj.
 
SPTA  SO23-12-1  Att. 2 19 15 4845 Material Required for Examination Question Source: Bank
 
Question #63 A Reactor Trip has occurred.' The crew is ready to report Standard Post Trip Actions.
 
Reactivity Control and Vital Auxiliaries have been reported.
 
Which of the following states the correct sequence for the next four (4) safety functions to be reported?
A. RCS Inventory Control RCS Pressure Control RCS Heat Removal Core Heat Removal B. RCS Inventory Control '      i RCS Pressure Control Core Heat Removal RCS Heat Removal C. RCS Pressure Control RCS Inventory Control.
 
Core Heat Removal RCS Heat Removal D. RCS Pressure Control RCS Inventory Control RCS Heat Removal Core Heat Removal Answer B Exarn Level B Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: 2.4.14 Krrwiedge of general guidelines for EOP flowchart use. RO Group:  SRO Group:
RO K/A 30  SRO K/A 3.9 Referonce Title Facility Reference Number Secticn Page Revision Learning Obj.
 
SPTA  SO23-12-1  Att.1 17 15 622 Material Required for Examination Question Source: Bank I
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Question #64        l l- Quench Tank level has been rising slowly.
 
l Which of the following annunciators would assist the operator in determining why Cus is  )
occurring?
l A. 50A32, PZR Spray Valve Bellows Seal Failure.
 
L. 50A35, Reactor Vessel Seal leakage.    ,
 
C. 56B59, RCP Bleedoff Relief Valve leaking.    !
D. 56C46, RCP Intergasket leakage.
 
Answer C Exam Level B Cognitive Level Memory  Facility San Onotre 2 & 3 Exam Date 4/16/99 Tier: 2.4.46 Ability to verify that the alarms are consi6 tent with plant RO Group:  SRO Group:
conditions.
 
RO K/A 3.5 SRO K/A 2.6 Reference Title Facility Reference Number Section Page Revision Leaming Obj.
 
Annunciator Panel SOA SO23-650.A2  50A31 9 5 6569 I
Material Required for Exam %ation Question Source: New
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Question #65
        -
Which of the following conditions will result in starting the LP Turbine Exhaust Hood Emergency Spray Water Pump following a Turbine Trip from 100% power?
A. Condensate supply press to the LP Spray system <100 psig and the LP Spray valve is open.
 
B. Depressing the " START" handswitch with a SIAS present.    ,
C. LP Exhaust Temperature >l60 Fon one or more exhaust hoods.
 
D. Depressing the " OVERRIDE" handswitch with a MSIS present.
 
i Answer A Exam Lovel B Cognitive Level Memory  Facility San Onofre 2 & 3 Exam Octe 4/16/99 Tier:(1) BW/A04 aa2.2 Adherence to appropriate procedures and RO Group: 2 SRO Group: 2 operation within the limitations in the facility's license and amendment.
 
J RO K/A 3.7 SRO K/A 4.4 Reference Title Facildy Reference Number Section Page Revision Learning Obj.
 
Turbine Protective SO23-10-4  6.4 14 6 Device Testing      5377 Material Required for Examination Question Source: Bank l
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. Question #66 Given the following:
-
  . An unisolable ESDE has occurred outside Containment
-
The affected S/G has blown dry
  .
RCS temperature is 350 F
-
Pressurizer pressure is 1290 psia The crew should:
A. Secure all running RCPs.
 
B. Stabilize RCS temperature and depressurize the RCS.
 
C. Reduce RCS temperature to establish 20 F subcooling.
 
D. Stabilize RCS pressure and temperature at current values.
 
Answer B cxam Level B Co0nitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (1) BW/E03 ea2.2 Adherence to appropriate procedures and RO Group: 1 SRO Group: 1 operation within the limitations in the facihty's hcense and amendments.
 
RO K/A 3.5 SRO K/A 4.0 Reference Title Facility Roterence Number Section Page Revision Learning Obj.
 
ESDE  SO23-12-5  12 15 6906 Material Required for Examination Steam Tables Question Source: New
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I' Question #67 i
: Given the following plant conditions:
 
l l  -
A small break LOCA is in progress and SIAS has actuated
  - All systems are operating as expected Per the stated conditions, which of the following is the basis for maintaining a secondary heat sink?
A. To mirimize boron stratification of the RCS.
 
B. RCS pressure may remain so high that cooling from the injection flow alone is inadequate to remove decay heat.
 
C. Reflux boiling is the primary means of heat removal prior to voiding in the hot legs.
 
D. To rmvide an attemative method of RCS pressure control.
 
Answer B Exam Level B Cogndive Level Memory  Facility San 0.1ofre 2 & 3 Exam Date 4/16/99 Tier: (1). BW/E04 ea2.1 Facility conditions and selection of RO Group: 2  SRO Group: 2 appropriate procedures during abnormal and emergency operations.
 
RO K/A 3.2 SR O K/A 4.4 Reference Title Facility Reference Number Section Page Revision Learning Obj.
 
LOCA Bases SO23-14-3  Att.1 10 4 4732 Material Required for Examination Question Source: New
 
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Question #68 Given the following:
  -
The unit tripped 30 minutes ago due to a LOCA
  -
RCS temperature is 525 degrees F
  -
Pressurizer pressure is 1600 psia
  -
Power has been lost to the switchyard
  --
lE power is being supplied by the diesel generators
  -
Voids have formed in the head For the given conditions, which of the following actions will be required to promote greater cooling in the reactor vessel head?
A. Stan a CEDM Cooling Unit.
 
B. Vent the head to the quench tank.
 
C. Start a Reactor.Coohmt Pump.
 
D. Alternately raise, then lower, RCS pressure.    .
Answer D Exam Level B Cognitive Level Application Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier:(1) BW/E08 ek3.3 Manipulaton of controls required to obtain RO Group: 2 SRO Group: 2 desired operating results during abnormal and emergency situations.
 
RO K/A 4.0 SRO K/A 3.9
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Reference Title Facility Reference Number Section Page Revision Learning Ott LOCA Bases SO23-14-3  Att.1 52 4 4732
' Material Required for Examination Question Source: NRC 6/98 l
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Question #69 -
Unit 3 is at 100% steady state power. The following data has been gathered conceming RCS leakage:
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        ,
        '
  -
3.9 gpm  leakage into the Quench Tank from RCGVS
  -
3.1 gpm . leakage into the Reactor Drain Tank from 3PV0100A
  -
  ; 1.8 gpm leakage past all check valves from RCS to SI system
  .
700 gpd  E088 S/G primar/ to secondary leakage  I
  -
10 gpd E089 S/G primary to secondary leakage
  -
0.8 gpm  leakage into Containment Sump    !
Which of the followir:g is true concerning the above RCS leakage per Technical Specifications?
. A. No Technical Specification entry required.
 
i B. Identified Leakage has exceeded the limit.
 
C. Unidentified leakage has exceeded the limit.
 
D. Primary to Secondary leakage has exceeded the limit.
 
Answer A Exam Level B Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99
 
Tier: (1) CE/A16 Generic 2.1.12 Ability to apply Technical Specifications RO Group:3  SRO Group:3 '
for a system.
 
RO K/A 2.9 SRO K/A 4.0 Reference Title Facility Refereru.e Number Section Page Revision Learning Obj.
 
' Technical  RCS OperationalLeakage 3.4.13 3.4-37 Specihcatons      6574 Material Required for Examination Question Source: New
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. Question #70 The following conditions exist on Unit 2:
  :
A LOCA has occurred
  - - SIAS, CIAS, and CCAS have actuated
  -
The STA reports that the Safety Function Status Check hr.s failed on Inventory Control Which of the following Containment Isolation Valve (s) FAILURE TQ CLOSE would cause a flowpath to outside of containment?
A. HV-5388 Instrument Air to Containment isolation Valve.
 
B.- HV-6223 Train A CCW Supply isolation Valve.
 
C. HV-9217 and HV-9218 RCP Bleed-off to VCT Isolation Valves.
 
D. HV-5434 Nitrogen Supply to SIT Isolation Valves.
 
Answer C Exam Level B Cognitive Level ' Application . Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier:(1) CE/E09 generic 2.4.21 Knowledge of the parameters and RO Group: 2 SRO Group: 2 logic used to assess the status of safety functions. f RO K/A 3.7  SRO K/A 4.3 Reference Title . Facility Reference Number Section Page Revision Le]< ning Obj.
 
LOCA Bases  SO23-14-3  Att.1 17 4 6932 Functional Recovery SO23-14-9  N.1 32 6 Bases    l
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Material Required for Examination Question Source: New
 
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g Question #71 A Shutdown From Outside the Control Room is being performed per SO23-13-2. Plant conditions are as follows:
  -
Pressurizer pressure is 2050 psia and slowly lowering
  -
T-hot is 575 F and slowly lowering
  -
T-cold is 555 F and stable
  -
Pressurizer level (actual) is 21 % and slowly lowering
  -
Charging is HQIestablished
  -
S/G E089 level (actual) is 58% narrow range    i Which of the following statements is correct concerning Natural Circulation for the current plant conditions?
  .A. Natural Circulation is not established because the plant parameters are outside the guidelines.
 
m B. Natural Circulation is established but cannot be verified until Pressurizer level is greater than 40%
C. Natural Circulation cannot be verified until manual control of the ADV's is established and T-cold is lowering.
 
D. Natural Circulation is established and may be verified.
 
Answer D Exam Level B Cognitive Level Application Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (1) CE/A13 aa2,1 Facility conditions and selection of appropriate RO Group: 1 SRO Group: 1 procedures during abnormal and emergency oporations.
 
RO K/A 2.7 SRO K/A 3.7 Reference Title Facility Reference Number . Section Page Revision Learning Obj.
 
shutdown From outsale SO23-13-2  Att.15 103 5 the Control Room 6774 Material Required for Examination: Steam Tables      >
- Question Source: NRC 6/98      ;
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- Question #72 Unit 2 has exoerienced a loss of Offsite Power. Following the subsequent Reactor Trip both i
S/G pressures are noted to be 760 psia and lowering.
 
What action should be taken?
A. Override and stop the turbine driven AFW pump. l B. Declare a cooldown in progress and reset the MSIS setpoints.
 
C. Shut the MSIVs.
 
,
D. Ensure MSR isolation valves closed.
 
Answer C Exam Level B Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/09 Tier:(1) CE/A11 ak2.1 Components and functions of control and RO Croup: 1 SRO Group: 1 safety systems including instrumentation,
        '
signals, interlocks, failure modes, automatic and manual features.
 
RO K/A 3.2 SR O K/A 3.4
    ..
Reference Title Facihty Reference Number Secton Page Revision Learning Obj.
 
SPTA  SO23-12-1  8 15 473[
Material Required for Examination Question Source: New i
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B i
H Question #73 The following conditions exist:
'
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A small break Loss of Coolant Accident has occurred
-
HPSI Pumps P018 and P019 have been stopped upon meeting HPSI 1hrottle/Stop Criteria
-
All three charging pumps are mnning
-
Pressurizer pressure is 1400 psia and steady  *
.
Core exit subcooled margin is 25 F
-
RCS cooldown is in progress
-
Pressurizer level is 28% and slowly lowering Which of the following is an appropriate action for these conditions?
A. Start HPSI Pump P019, and throttle open HPSI Injection valves to restore Pressurizer level.
 
B. Start HPSI Pump P018 and P019 in preparation for reinitiating injection if Pressurizer level continues to decrease.    .
 
1 C. Reduce the RCS cooldown rate to allow Pressurizer level to recover.
 
D. Start HPSI ? umps Pol 8 and P019, and fully open all HPSI Injection valves until subcooled margin is restored.
 
I
 
Answer A Exam Level B Cognitive Level Application Facility San Onoire 2 & 3 Exam Date 4/16/99 Tier: (1) W/E02 ek2.2 Facihty's heat removal systems, including RO Group: 2 SRO Group: 1 primary coolant, emergency coolant, the decay heat removal systems and relatsns between the proper operaten of these systems to the operationof thefacility.
 
RO K/A 3.5 SRO K/A 3.9 Reference Title Facility Reference Number Section Page Revision Learning Obj.
 
LOCA'  SO23-12-3  Att. 2 45 15 6511 Material Required for Examination Question Source: New      ;
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Question #74 '
Given the following plant conditions:
-
The plant is ~at 100% power
-
2FI-0212, charging flow indication is reading 15 GPM
-
Radwaste Operator reports a leak in the charging header between Charging Header Isolation valve, S21208MUO91, and Containment Isolation valve 2iiV-9200 Which of the following flow paths could provide flow using a charging pump to the Reactor Coolant System?
A. LPSI header.
 
B. HPSI header.
 
C. Auxiliary Spray Flow header.
 
D. Charging Header Spring loaded Check Valve 2XCV9219.
 
Answer B Exam Level B Cognitive Level Application Facility San Onofre 2 8 3 Exam Date 4/16/99 Tier: (1) W/E04 EK2.1 Components and functions of control and RO Group: 2 SRO Group: 1 Saf ety systems, including instrumentation, signals, interlocks, failure modes, automatic and manual features.
 
RO K/A 3.5 SRO K/A 3.9 Reference Title Facility Reference Number Section Page Revision Learning Obj.
 
RCS Leak SO2313-14  3.3.2 8 2 2907 Material Required for Examination Question Source: New w
 
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Question #75 i
l Given the following plant conditions:      I
--
E088 S/G pressure is 725 psia
!'
  -
E089 S/G pressure is 1000 psia
-- Pressurizer pressure is 1600 psia    '
-
Containment pressure is 12 psig    l
-
Containment Hi Range Radiation monitors read 13 R/hr and increasing  )
-
No' operator actions has been performed    i Given these conditions, which of the following ESFAS Actuations simuld NQIhave  l automatically initiated?
- A. CRIS.      I B. SIAS.      .
I
        ;
C. MSIS.      *
D. CSAS.
 
l l
Answer D Exam Level B Cognitive Level Comprehension Facihty San Onofre 2 & 3 Exam Date 4/10W9 f
Tier: (1) W/E 16 Ek2.1 Components and functions of control and RO Group: 2 SRO Group: 2 I safety systems, including instrumentation, signals, interlocks, f ailure modes, automatic and manual features.
 
RO K/A 3.0 SRO K/A 3.3 Reference Title Facility Reference Number Section Page Revision Learning Obj.
 
Annunciator Panel 57A SO23-15-57A  57A03 13 4 5375 Material Required for Examination      j Question Source: New      i i
 
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. Question #76 -
A plant stanup is in progress and the following conditions exist:
  -
The reactor is critical at 5E-5% power
  -
Tave is at 545 degrees F
  -
RO inadvenently withdraws Group 5 CEAs from 35" to 55"
  -
No reactor trip occurs Which of the following describes the effect that this event will have on reactor parameters over the NEXT MINUTE?      -
A. Reactor Power will rise, the response of Tave will depend upon core life.
 
B, Reactor Power and Tave will both rise.
 
-
C. Reactor Power will be unaffected, Tave will rise.
 
D. Reactor Power will rise, Tave will be unaffected.
 
Answer L 0 l Exam Level R Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/1S/99 Tier:(2) .001 f.1.06 Reactor Power  RO Group: 1 SRO Group:
  '
RO K/A 4.1 SRO K/A ReferenceTitle ~ Facility Reference Number Section Page Revision Learning Obj.
 
.
Generic Fundamentals 793l
. Material Required for Examination
- Question Source: New-
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Question #77 Given the following:
'
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  --
Chairman, Board of Supervisors County of San Diego
  ' A Loss of Coolant Accident has occurred at Unit 2
  -
SO23-12-3 is being implemented
  -
The ACO has been directed to STOP all Reactor Coolant Pumps (RCPs)
  -
RCP. 2P001 fails to stop when the STOP pushbutton is depressed Which of the following is the appropriate action for stopping 2P00l?
A. - Dispatch an operator to open the' breaker to 2P001 locally, at the bus.
 
B. Dispatch an operator to verify locally that DC power is aligned to 2P001 breaker.
 
C. Deenergize 2A01 by opening the supply breaker from the Reserve Auxiliary Transformer.
 
D. Decnergize Reserve Auxiliary Transformer 2XR3 by opening the breakers from the switchyard.
 
Answer. C . Exam Level R Cognitive Level Application Facility San Onofre 2 & 3 Exam Date 4/16/99 I Tier: (2) 003 k2.01 RCPS  RO Group: 1  SRO Group:
l RO K/A 3.1 SRO K/A j Reference Title  Facility Reference Number Sectio Page Revision teaming Obj. ;
        ,
*
Conducts of Operations SO23-0 46  6.16.3' 18 0 74gg Transferring 6.9 KV Buses SO23-61  6.8 11 4 Material Required for Examination
. Question Source: NRC 6/98      ,
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- Question #78 The following conditions are presenti
  --
Channel A low DNBR trip is bypassed
  -
RCP P001 flow input to CPC Channel B has failed low
'Which of the following conditions will result in a reactor trip?
A. ' Imp I hot leg temperature input to Channel B CPC fails high.
 
B. Imp I hot leg temperature input to Channel A CPC fails low.
 
C. Pmssurizer pressure input to Channel B CPC fails hi;h.
 
' D. Pressurizer pressure input to Channel C CPC fails low.
 
Answer D Exam t.evel R Cognitive Level Comprehension
    '
Facility San Onofre 2 & 3 Exam Date 4/16/99 3/13/99 Tier: (2) 012 RPS K4.02 Automatic 3eactor Tnp when RPS RO Group: 2 SRO Group:
setpoints are exceeded for each RPS function; basis for each RO K/A 3.9 - SR O K/A Reference Title Facility Reference Number Section Page- Revision Learning Obj. I Plant Protection DBD-SO23-710  2.1.1 70 2 System -
4936 Material Required for Examination Question Source: New l
 
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. Question #79 he following sequence of events occurs:
J
  -
A LOCA has occurred      j
  -
  - A Safety injection Actuation Signal (SIAS) has started all required ECCS pumps  j
  -
The diesels are runr.:ng unloaded    I
  -
  -
5 minutes after the SIAS, offsite power is lost Which of the following describes the expected response of the ECCS pumps subsequent to the
    '
J Loss of Offsite Power?      l A. All required ECCS pumps restart immediately after their train's EDG output
'
breaker closes, i
 
-
B. The SIAS wiii need to be manually actc.ted to allow all the required ECCS pumps to automatically start.
 
~ C. All required ECCS pumps will restart in time delayed sequence.
 
D. The SIAS will have to be reset and the required ECCS pumps started by operator  l action.'
f Answer C Exam Level R Cognr.ive Levet Comprehension Facility San Onofre 2 & 3 ' Exam Date 4/16/99 !
Tieri (2) 013 kl.01 - Initiation signals for ESF circuit logic RO Group: 1  SRO Group:
RO K/A 4.2 $RO K/A Reference Title Facihty Reference Number Section Page Revision Learning Obj.
 
Elementary Diagram 30643    7 10397 Material Required for Examination
- Question Source: New -
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Question #80 Which of the following statements accurately describes the Power Trip Test Interlock (PTTI) in  I the Excore Safety Channel System?      )
        )
A. Simulates a 200% linear power output causing a PPS high linear power trip in the j affected channel.      I l
B. Actuates the LO DNBR and HI LPD CPC trips for the affected channel.  '
C. Prevents more than one channel of log power being simulated greater than 1.0E-4% power during testing. l i
D. Gives permissive to manually bypass the LO DNBR and HI LPD CPC trips when reactor power lowers to less than 1.0E-4%.    ,
l Answer B Exam Level R Cognitive Level Memory Facility San Onofre 2 8 3 Exam Date 4/16/99 Tiet: (2) 015 k3.01 RPS  RO Group: 1 SRO Group:
RO K/A 3.9 SRO K/A Explanation of Answer Reiszence Title Fae hty Reference Number Section Page Revision Learning Obj.
 
Reactor Protective SO23-3-2.12  6.8.6 17 7 System Operation      7175 Material Required for Examination Question Source: New m -
 
Question #81 i
Which of the following is an indication that Natural Circulation flow may be lost during EOl implementation?
A. ~ RCS pressure greater than Saturation pressure of the Steam Generator.
 
*
B. T-hot rising with constant T-cold.
 
C. Delta-T (Core Exit Hermocouple minus T-hot) equal to 10 F.
 
D. Delta-T(T-hot minus T-cold) of 28 F.    ;
Answer B Exam Level R Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier:(2) 017 a3.01 Indications of normal, natural, and interrupted RO Group: 1 SRO Group:
circulation of RCS.
 
PO K/A 3.6 SRO K/A Reference Title Facility Referetco Number Section Page Revision Learning Obj.
 
SPTA  SO23-12-1  6 15 g    2536 Material Required for Examination Question Source: Bank
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l-L QuesGon #82 Given the following plant conditions:
-
Unit 2 is at 100% power when an inadvertent SIAS occurs
-
Reserve Auxiliary Transformer 2XR1 relays on sudden pressure
-
Diesel Generator 20002 started and is loaded on bus 2A04
- Diesel Generator 20003 started and tripped 15 seconds later Which of the following is performing the containment cooling function?
A. Containmen't Normal and Emergency Coolers.
 
B. Containment Normal and Train "A" Emergency Coolers.
 
C. Both Train "A" and "B" Containment Emergency Coolers.
 
D. Only Train "A" Containment Emergency Coolers.
 
Answer D Exam Level R Cognitive Level Comprehension Facihty San Onofre 2 & 3 Exam Date 4/16/99 Tier; (2) 022, K2.01 containment coohng system cookng fans RO Group: 1- SRO Group:
RO K/A 3.0 SRO K/A Reference Title Facihty Reference Number Section Page Revision Learning Obj.
 
Elementary Diagrams 31248,31249,31250,  14,15,14,15,7 31251,31269 7367 Material Required for Examination Question Source: New
 
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Question #83 Given the following plant conditions:
f
  -
Unit 2 operating at 100% power
  -
CCW pump 2P-025 in service and aligned to Train B for single train operation
  -
A ground fault causes a Irss of 4KV Bus 2A06 What operator actions are required to restore CCW to the RCPs?
A. Ensure start of CCW pump 2P-024 and SWC pump 2P-307.
 
B. Ensure stan of CCW pump.2P-026 and SWC pump 2P-114.
 
C. Ensure start of CCW pump 2P-024 and transfer Non-critical Loop.
 
D. Ensure start of CCW pump 2P-026 and transfer Non-critical loop.
 
Answer C Exam Level R Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (1) 026 aa2.02 The cause of possible CCW loss RO Group: 1 SRO Group:
RO K/A 2.9 SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Obj.
 
Loss of CCW/SWC SO23-13-7  3.5 6 3 6739 ,
Material Required for Examination Question Source: New
 
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l Question #84 -
Given the following:
- Unit 2 is in MODE 6.'
- The core is being off loaded to the SFP.
 
- The OPERABLE Containment Purge valve, HV-9949, is determined to be stuck in the open position.
 
What action is required per Technical Specifications LCO 3.9.3, Containment Penetrations?
A. Immediately place containment mini-purge in operation.
 
B. Isolate the affected purge flowpath within 4 hours.
 
C. Deenergize the affected valve within I hour.
 
D. Immediately suspend core alterations and movement ofirradiated fuel.
 
Answer D .. t!xam Level R Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier:(2) 028 Generic 2.1.12 Ability to apply Technical Specifications RO Group: 3 SRO Group:
to a system RO K/A 2.9 SRO K/A Reference Title Facili*y Reference Number Section Page Revision Learning Obj.
 
Technical' Containment Penetrations LCO 3.9.3 3.9-4 7375 Specifcations '
Material Required for Examination Question Source: New
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Question #85 Which of the following will cause an actuation that closes the containment main purge isolation valves?
A; High Containment Pressure.
 
B. High Containment Temperature.
 
C. High Containment Radiation.
 
D. Low Pressurizer Pressure.
 
Answer C Exam Level R Cognitive Level Mcmory  Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (2) 029 K103 Engineered Safeguards  RO Group: 2 SRO Group:
RO K/A 3.6 SRO K/A
' Reference Title  Facility Reference Number Section Page Revision Learning Obj.
 
._
Containment Airborne Radiatier, SO23-3-2.24.11 4.3 4 12 7303 Morutor System Operation Material Required for Examination Question Source: New
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Question #86 Which of the following is the IRAST preferred source of makeup to the Spent Fuel Pool?  )
i A. Primary Makeup Water (PMW).'    j
. B. Boric Acid Makeup Tanks (BAMU). I
        !
C. ' Refueling Water Storage Tanks (RWST).
 
D. Nuclear Service Water (NSW).
 
, , - _
Answer . D Exam Level R Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier,- ( 2) 033 SFPCS A2.01 inadequate SOM RO Group: .2 SRO Group:
RO K/A 3.0 SRO K/A .
I
        '
Reference Title Facility Reference Number Section Page Revision Learning Obj.
 
Spent Fuel Purifcation SO23-3-2.11.1  6.1 3 6 Cross-tie Operation 4589 '"
        -
i Material Required for Examination Question Source: New
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1600 Pacific Highway, Room 335    l San Diego, California 92101 l
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  % s R. Watts, Esq.
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s c.
 
Question #87 Given the following plant conditions on Unit 3:
  -
SG Generator E-088 has a known Primary to Secondg Mak of 0.3 gpm
  -
SG Generator E-089 has a known Primary to Seconday y ak of 0.4 gpm Which C the following actions is required by Technical Specifications?
A. No action required.
 
B. Commence a controlled plant shutdown.
 
C. Commence a rapid plant shutdown.
 
i J
. D. Manually trip the reactor and perform SPTAs.
 
Answer A Exam 8 evel R CognitiveLevel Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier; (1) 037 aa220 Tech Spec Aimits for RCS leakage. RO Group: 2 SRO Group:
RO K/A 3.2 SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Obj.
 
i Technical RCS Operational Leakage 3.4.13 3.4-37  g3g j Specifcations      i l
      ,
Material Required for Examination Question Source: New l
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Question #88 Given the following:
  -
Unit 3 is at 5% power
-
Temperature is being maintained by the Steam Bypass Control System
-
The isothermal Temperature Coefficient OTC) is POSmVE
-
  ' A total loss of condenser vacuum occurs  -
-
All systems are in automatic Which statement correctly describes Reactor response?
A. Positive reactivity will be added, reactor will eventually trip on VOPT.
 
B.
 
'
Negative reactivity will be added, reactor power will stabilize above the point of adding heat.
 
'
C. Negative reactivity will be added, reactor power will stabilize below the point of adding heat.
 
D. Positive reactivity will be added, reactor power will increase until the Main Steam Safety Valves lift.
 
Answer D Exam Level R Cognitive Level Apphcation Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier:(2) 039 k5.08 Effect of steam removal on reactivity. RO Group: 2 SRO Group:
RO K/A 3.6 SRO K/A Reference Title Facihty Reference Number Section Page Revision Leaming Obj.
 
Generic Fundamentals 4354 Material Required for Examination Question Source: Bank h
 
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! Question #89
        )
he reactor trips from 100% power. We operators verify that the reactor is tripped and immediately note that the turbine has not tripped and the generator breakers remain closed.
 
I Which of the following statements describes potential consequences of this event?  l A. A loss of subcooling, resulting in the need to trip all RCPs.
 
B. An uncontrolled cooldown of the RCS, resulting in less shutdown margin.
 
C. A decrease in RCS inventory, resulting in core uncovery.
 
D. An increase in RCS pressure, possibly resulting in the Pressurizer safety valves  !
lifting.
 
Answer B Exam Level R Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (2) 045 a1.05 Expated response of primary plant RO Group: 3 SRO Group:
parameters (temperature and pressure)
following T/G trip.
 
RO K/A 3.8 SRO K/A Reference Title Facihty Reference Number Section Page Revision Learning Obj.


SPTA Bases SO23-14-1  Att.1 10 4 8026 Material Required for Examination Question Source: New
<etodruff, Spradlin & Smart 7T S. Parker St. Suite 7000 Ora ige, Califomia 92868-4720    /
        .
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s Sherwin Harris, Resource Project Manager Public Utilities Department      l City of Riverside 3900 Main Street Riverside, California 92522
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- Question #90 Given the following:
-
2RT-7870 Condenser Air Ejector Radiation Monitor setpoint is 1.05E-0
- Secondary Radiation HI alarm actuates
-
5 minutes later 2RT-7870 indicates 2.20E-0 Which of the following actions is required for the above conditions?
A. Manually trip the reactor and carry out the SPTAs.


B. Commence a controlled plant shutdown and insert rods below 5% reactor power.
    -
 
    ,_ _ i San Onofre Nuclear Generating Station -3-R. W. Krieger, Vice President Southem California Edison Company San Onofre Nuclear Generating Station P.O. Box 128 San Clemente, California 92674-0128
C. Commence a rapid plant shutdown and trip the unit at 35% reactor power.
  . Stephen A. Woods, Senior Health Physicist Division of Drinking Water and Environmental Management Nuclear Emergency Response Program Califomia Department of Health Services P.O. Box 942732, M/S 396 Sacramento, California 94334-7320 Mr. Michael R. Olson Sr. Energy Administrator-
 
  . San Diego Gas & Electric Company P. O. Box 1831
D. Remain at power, sample all SG's and perform a leakrate calculation.
 
Answer C Exam Level R Cognitive Level Application Facility San Onofre 2 & 3 Exam Date 4/Ir>99 Tier: (2) 055 K1.M PRM system  RO Group: 2 SRO Group:
RO K/A 2.6 SRO K/A Reference Title Facility Reference Number Section Page Revison Learning Obj.
 
Reactor Coolant Leak SO23-13-14  3.4.7.4 15 2 l 8201 Material Required for Examination Question Source: NRC 6/98
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Question #91      l Given the following plant conditions:
  -
Unit is initially operating at 100% power    l
  -
Condensate Pumps P050, P051 and P052 are initially nmning  j
  -
Condensate Pump P050 trips    1 Which of the following automatic actions should occur?
A. lienter Drain Pumps will trip on low HDT level B. Condensate Pump P053 will auto stan.
 
C. Recirculation valve for Condensate Pump P050 will auto close,   j D. Main Feedwater Pumps will trip on low suction pressure.
 
Answer B Exam Level R Cognitive Level Comprehension Facility San Onofre 2 & 3 Ftam Date 4/16/99 Tier:(2) 056 a2.04 Loss of condensate pumps RO Group: 1 SRO Group:
RO K/A 2.6 SRO K/A l l
Reference Title Facility Reference Number Secton Page Revision Leaming Obj.
 
Condensate Pump SO23-2-2  Att. 2 23 9  I 5364 Operation Material Required for Examination
  ' Question Source: New l
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l l. Question #92
 
l Given the following plant conditions:      ;
  -
Unit 2 is operating at 100%
  -
Vital Bus Inverter 2Y002 has just failed, deenergizing vital bus 2Y02 Which of the following is correct conceming Auxiliary Feedwater Flow to the steam generators?  1 A. Only one S/G is being fed.
 
B. No AFW components change state.
 
C. Both S/Gs are being fed.
 
D. P-140 mnning, neither S/G is being fed.
 
Answer A- Exam Level R Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 4/16/99 Tier: (1) 058 aa2.03 DC loads lost; impact on abihty to operate and RO Group: 2  SRO Group:
monitor plant systems.
 
RO K/A 3.5 SRO K/A Reference Title  Facihty Reference Number Secton Page Revision Learning Obj.
 
RPS FAILURE / LOSS OF VITAL SO12-13-18  ATT2 17 of 24 2 BUS INVERTER l3644 l
Material Required for Examination      ;
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Question #93 A loss of all Feedwater has occurred. Upon restoring Feedwater, the operator opens the MFW Regulator Bypass Valves to 20% for 5 minutes.
 
Why are these actions necessary?
'
        \
l  A. Prevents rapid cooldown of the RCS.
 
I        i B. Allows equalizing temperature across the S/G.
 
j  C. Minimize the possibility of a water hammer event to the tubesheet.
 
i
 
  'D. Ensures S/G feedring is slowly refilled.
 
Answer D l Exam Level R Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier:(2) 059 a2.04 Feeding a dry S/G  RO Group: 1 SRO Group:
        '
RO K/A 2.9 SRO K/A Referete Title Facihty Reference Number Section Page Revision Learning Obj.
 
Lossof Feedwater SO23-14-6 Att.1 14 4 Bases 4734 Material Required for Examination Question Source: Bank i
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Question #94 An Emergency Diesel Generator (D/G) monthly surveillance test is being performed. D/G load is indicating 4.7 MWs.
 
Which of the fohowing is correct?
A. D/G load is below the allowable range of the acceptance criteria, and above the minimum limit for diesel loading.
 
B. D/G load is within the allowable range of the acceptance criteria.
 
t C. D/G load is above the allowable range of the acceptance criteria, ard c.:10w the maximum limit for diesel loading.
 
D. D/G load is above the maximum limit for diesel loading.
 
I l
Answer B Exam Level R Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (2) 062 A1.01 Significanceof D/Gloadlimits RO Group: 2 SRO Group: l l
R O K/A 3.4 SRO K/A Reference Title Facility Reference Number Section Page Revision Learnira Obj.
 
Diesel Generator SO23-3-3.23  Att 1 21 14 ggg7 Monthly Test Material Required for Examination Question Source: New l
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San Diego, Califomia 92112-4150 Mr. Steve Hsu Radiological Health Branch State Department of Health Services P.O. Box 942732 Sacramento, California 94234
 
  <
        )
Mayor City of San Clemente 100 Avenida Presidio San Clemente, California 92672
Question #95      q l
l The Control Room was evacuated 15 minutes ago due to dense smoke. A shutdown from
        '
l outside the control room is in progress. I l
Which of the following lists the PREFERRED components to be used to establish auxiliary feedwater to steam generator E0897 (Assume all AFW components are available)    ,
l A. 1) HV-4763 P141 discharge bypass valve    1 2) HV-4731 AFW isolation valve 3) P141 motor driven AFW pump B. 1) HV-4706 P140 discharge to E089 2) HV-4731 AFW isolation valve 3) Pl40 steam driven AFW pump
 
I C. 1) HV-4713 P141 discharge valve    {
2) HV-4731 AFW isolation valve    I 3) P141 mc, tor driven AFW pump i
D. I) HV-4706 Pl40 discharge to E089 t
2) HV-4715 AFW isolation valve
        )
j 3) Pl40 steam driven AFW pump
        ]
Answer C' Exam Level R Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier:(1) 068 aa1.03 S/G level  RO Group: 1 SRO Group:
RO K/A 4.1 SRO K/A Reference Title Facility Reference Number Section Page Revision Leaming Obj.
 
Shutdown from Outside SO23-13-2  Att. 6 47 5 the Control Room 9444 z Material Required for Examination Question Source: New l
 
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i. Question #96 I
i        i l Which of the following would be the PREFERRED discharge path per SO23-8-7, Liquid
[ Radioactive Waste Release Operations, when performing a radioactive liquid effluent release?
A. Unit 2 with Circulating Water pumps P115 anJ P117, and Saltwater Cooling pump 2P307 running.
 
B. Unit 2 with Circulating Water pumps PI 15, P116 and P t 18 running.
 
C. Unit 3 with Circulating Water pumps P115, PI 16, and Pl 17 running.
 
D. Unit 3 with Circulating Water pumps P116 and Pl 18, and Saltwater Cooling  j pump 3P112 running.      !
Answer C Exam Level R Cognitive Level Memory . Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier:(2) 068 Generic 2.1.32 Ability to explain and apply all system RO Group: 1 SRO Group:
limits and precautions RO K/A 3.4 SRO K/A Reference Title  Facility Reference Number Section Page Revision Learning Obj.
 
Liquid Radioactive Waste Release SO23-8-7  Att. 9 127 10 Operatens      9066 j
Material Required for Examination
- Question Source: New i
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l I Question #97 l
l Which of the following conditions represents a violation of Containment Systems as dese.ibed in I Technical Specifications?
A. While at 100% power, a mechanic blocks open the outer containment airlock door for 2 hours to perform maintenance activities on the INOPERABLE inner containment door.
 
B. While performing OPERABILITY tests en the redundant containment Loop i Hot Leg Sample valves (IIV 0508 and 11V 0509) at 100% power, one of the two
*
valves (HV-0508) fails to completely close.
 
C. While at 100% power, the nitrogen supply isolation valve to the Safety Injection Tanks isolation valve (HV-5434) fails its required stroke time.
 
D. While at 100% power, the outer containment airlock door fails its leak rate test and has to be opened to facilitate repairs that will take 2 hours.
 
Answer A Exam Level R Cogr.itive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/1049 Tier: (1) 069 aat.01 Isolation valves, dampers and RO Group: 1 SRO Group:
electropneumatic devices.
 
RO K/A 3.5 ERO K/A 1 Reference Title Facility Reference Number Section Page Revision Learning Obj. l Technical Containment Air Locks 3.62 3.6-3  6235 Specifications Material Required fer Examination Question Source: New f
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Question #98 What is the Instrument Air header pressure at which the Respiratory and Service Air System  I (RSAS) backup supply will automatically begin to supply the instrument air header?
l A. 61 - 70 psig.
 
l B. 71 - 80 psig.
 
C. 81 - 90 psig.
 
D. 91 - 100 psig.
 
Answer C Exam Level R Cognitive Level Memory Facihty San Onofre 2 & 3 Exam Date 4/16/99 l
Tier: (2) 079 A4.01 Cross-tie valves with lAS. RO Group: 2 SRO Group:
RO K/A 2.7 SRO K/A Reference Title Facihty Reference Number Section Page Revision Learning Obj.
 
]
Instrument Air System SO23-1-1  6.12 14 12 Operation      653i l
Material Required for Examination l
Question Source: New
 
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Question #99 The FIRST action that the Operations leader performs after an Alert has been declared is:
  ;
l  A. Station someone on the Ivory Phone.
 
B. Evacuate personnel from Hazardous areas.
 
l l C. Activate the Emergency Response Data System.
 
D. Perform siren and PA ~ coordination.
 
l l Answer D Exam Level R Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 l      4/16/99 Tier: 2.4.29 Knowledge of the emergency plan. RO Group:  SRO Group:
RO K/A 2.6  SRO K/A Reference Title Facihty Reference Number Section Page Revision Learning Obj.
 
Operatons Leader SO23 Vill-30  6.1.1.1 4 3 Duties      857 Material Required for Examination Question Source: Bank l
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l Question #100 A Main Steam Line Break inside Containment has occurred.
 
Assuming proper operation of ESFAS Systems and equipment, what is the maximum expected Containment pressure by design?
'
        )
A. Approximately 37 psig.
 
B. Approximately 47 psig.
 
C. Approximately 57 psig.
 
D. Approximately 67 psig.
 
Answer C Exam Level R Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/1f#99 Tier: (1) CE/EOS - eki.2 Normal, abnormal and emer9ency RO Group: 1 SRO Group:
operating procedures associated
        *
with Excess Steam Demand.
 
RO K/A 3.2 SRO K/A Reference Title Facility Reference Number Secten Page Revision Learning Ott Technical Containment  B3.6.1 B3.6.1 Specifications      7530 Material Required for Examination Question Source: NRC 6/98 i
l l
 
E
 
l- ' Question #101
 
l
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After securing a Reactor Coolant Pump, what positive indication is available in the Control Room of the RCP being completely stopped?
l  A. RCS How low alarm.
 
B. Green stop light on.
 
l  C. Zero (0) amps indicated.
 
D. Zero speed light on.
 
.
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Answer D Exam Level S Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16FJ9 Tier: (1) 011 EA1,03 Secunngof RCPs  RO Group:  SRO Group: 1 RO K/A  SRO K/A 4.0 Reference Title Facility Reference Number Section Page Revision Learning Obj.
 
Reactor Coolant Pump SO23-3-1.7  6.3.6 8 21 Operaton      5389 i l
Material Required for Examination      ;
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! Question #102 Plant conditions are as follows:
  -
Unit 2 at 100% power      l
  -
Channel A 2PI-0101-1 Narrow Range Pressure has failed high  j
  -
Channel B 2PI-0102-2 Wide Range Pressure has failed low
  -- 'All actions of SO23-13-18, Reactor Protection Syster.1 Failure, have been
  . completed Which of the following correctly states the existing coincidence logic to trip the reactor on high Pressurizer Pressure?      ;
l A. I out of 2.
 
B. I out of 3.
 
C. .2 out of 3.      l
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D. 2 out of 4.      l
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Answer C Exam Level S Cognitive Level Comprehension . Facility San Onofre 2 & 3 Exam Date 4/16/99
        '
Tieri (2) 012 K4.02 ' Automate reactor trip when RPS setpoints are RO Group:  SRO Group: 2 exceeded for each RPS functon; basis for each.
 
RO K/A  SRO K/A 4.3 Reference Title Facility Refere'nce Number Section Page Revision Learning Obj.
 
Technical  RPS Instrumentation B3.3.1 B3.3-3 7297 Specifications Material Required for Examination Question Source: New
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(Question #103-r Given the following information on Unit 3:
  -
Reactor power- 100%
  - 92 day ESFAS logic matrix relay testing is in progress
  - Control Room airborne radiation monitor RE-7824 is in BYPASS for maintenance
  -
During the performance of the logic matrix test, the trip matrix being tested was prematurely de-energized, resulting in Trains "A" & "B" SIAS and CCAS actuation Which of the following is the expected systems response to the above conditions?
i A. CRIS actuation is blocked.
 
'
B. CRIS occurs on Train "A" only,    i
; C. CRIS occurs on Train "B" only.
 
<
I D. CRIS occurs on both Trains.
 
I Answer D Exam Level S Cognitive Level Comprehension Facihty San Onofre 2 & 3 Exam Date 4/16/99 Tier: (2) ~013 kl.01 Initiation signals for ESF circuit logic. RO Group:  SRO Group: 1 RO K/A  SRO K/A 4.4 Reference Title -  Facility Reference Number Section Page Revision Learning Obj. !
I Control Room Airborne Process . SO23 3-2-24.6  4.6 4' 5 6999 l Radiation Monitonno System Operation Material Required for Examination Question Source: NRC i1/98
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Question'#104 What is the basis for the Shutdown Margin requirement of 3% Delta K/K with T-ave less than 200 F?
A. Removal of the CEAs during refueling.
 
B. Reactivity effect from funher cooldown to Mode 6.
 
' C. A potential dilution event.
 
D. Allow for errors in enrichment of the new fuel load.
 
Answer C Exam Level S Cognitive Level Memory  Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (1) 024 Generic 2.1.12 Ability to apply Technical RO Group:  SRO Group: 1 Specifcations for a system RO K/A  SRO K/A 4.0 Reference Title Facility Reference Number Section Page Revision Learning Obj.
 
Techncal Shutdown Margin  83.12 B3.1-7 Specifcatons      6957 Material Required for Examination .
Question Source: Bank
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. Question #105 Which of the following valves would be throttled open by the operator to increase the RCS cooldown rate with Shutdown Cooling in service?    1 l
A. Shutdown Cooling Heat Exchanger inlet valve.
 
'
l B. Shutdown Cooling Heat Exchanger outlet valve.
 
C. Shutdown Cooling Heat Exchanger CCW outlet valve.
 
D. Shutdown Cooling Heat Exchanger CCW inlet valve.
 
I Answer B Exam Level S Cognitrve Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (1) 025 AA1.01 RCS/RHRS cooldown rate. RO Group:  SRO Group: 2 RO K/A  SRO K/A 3.7 Reference Title Facility Reference Number Section Page Revision Learning Obj.
 
SDC System Operation SO23-3-2.6  62.8.2 8 15  i 8036 Material Required for Examination Question Source: Bank      {
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Question #1%    ,
The plant has just tripped from 50% power operation, the SirTAs are being carried out and plant conditions are as follows:
  - Pressurizer pressure is 650 psia
  - Containment average temperature is 251 F
  -
Both S/G levels 40% NR
  -
Both S/G pressures 800 psia Which ESFAS signal combinations should have automatically actuated?
A. . EFAS, RAS, SIAS.
 
B. CSAS,' SIAS, CIAS.
 
C. SIAS, CIAS, EFAS.
 
SIAS, MSIS, CSAS.
 
'
' D.
 
Answer B Exam Level S CognitiveLevel Comprehension Facility San Onotre 2 & 3 Exam Date 4/16/99 Tier: (2) 026 A1.01 Containment pressure  RO Group:  SRO Group: 1 RO K/A  SRO K/A 42
  '..
Reference Title Facility Reference Number Section Page Revision Learning Obj.
 
Technical  ESFAS Instrumentation 3.3.5 3.3-26  7303 Specifications
: Material Required for Examination Question Source: New
 
r-Question #107 l Both trains of CCW/SWC are in operation.
 
l What is the reason for aligning the 12tdown Heat Exchanger to the Critical loop that is supplying the Non-Critical loop?
A. Reduces the potential for RCP seal deterioration by minimizing the temperature differential in the Non-Critical imp.
 
B. Maintains heat load requirements distributed evenly between the loops.
 
C. Sets loop flows to match operating pressures of the loops to minimize cross train leakage.
 
D. Ensures that CCW process radiation monitor is aligned to detect any letdown Heat Exchanger tube leakage.
 
Answer D Exam Level S CognitiveLovel Memory Facility San Onotre 2 & 3 Exam Date 4/16/99 Tier: (1) 026. AA2.02 The cause of possible CCW loss. RO Group:  SRO Group: 1 l
RO WA  SRO WA 3.6 Reference Title Facility Reference Number Section Page Revision Learning Obj.
 
CCW System SO23-2-17  Att. 7 56 12 Operation 6257 Material Required for Examination Question Source: NRC i1/98
 
m J
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il Question #108 The following conditions exist:
  -
A large break LOCA occurred on Unit 216 hours ago
  -
  ' SO23-12-3, " Lass of Coolant Accident" is being implemented.
 
-
11ydrogen Monitors initially indicated 0.7%.
  -
Following calibration Hydrogen concentration indicates 2.6%.
  - All ESFAS equipment is available and functioning normally.
 
Which of the following actions is required to satisfy the Containment Combustible Gas Control safety function of SO23-12-3?
I A. Ensure both Hydrogen Recombiners energized and Containment Spray in service.
 
B. Ensure the Hydrogen Purge System in service and all Containment Dome Air Circulating Fans operating.
 
, C. . Ensure both Hydrogen Recombiners energized and all Containment Dome Air  )
Circulating Fans operating. I i
D. Ensure both Hydrogen Recombiners energized and Hydrogen Purge System in scryice.
 
Answer C Exam Level S Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier:(2) 028 Generic 2.1.20 Ability to execute procedure steps RO Group:  SRO Group: 2 RO K/A  SRO K/A 4.2 Reference Title Facility Reference Number Section Page Revision Leaming Obj.
 
LOCA  SO23-12-3  Alt.1 26 15 2548
' Material Required for Examination Question Source: New
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Question #109      ,
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Which of the following radiation monitors will cause the initiation of the Containment Purge Isolation Signal (CPIS)? .
A. RE-7828 Containment Purge Stack Radiation Monitor.
 
B. RE-7820 Containment fligh Range Radiation Monitor.
 
C. RE-7808 Plant Vent Stack Radiation Monitor. j D. RE-7804 Containment Airborne Radiation Monitor.
 
Answer D Exam Level S Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/ICW9 4 Tier: (2) 029 K1.03 Engineered safeguards RO Group:  SRO Group: 2
  . RO K/A  SRO K/A 3.8 Reference Title Facility Reference Number Section Page Revision Learning Obj.
 
Containment Purge and SO23-142  Att.13 73 22 7550 Recirculation Filtration System Material Required for Examination      .
Question Source: Bank      j
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Question #110 Given the following:
i- 1 The plant is in MODE 3
-
A reactor startup is in progress -
-
Reactor power is at 2E-7%
-
CEAs are being withdrawn
-
Subsequently BOTH startup channels fail to zero Which of th'e following describes the action (s) to be taken?
A. Continue approach to criticality using safety channel power indication,  i
 
B. Immediately trip the Reactor.
 
C. Immediately stop all positive reactivity additions.
 
D. Commence a reactor shutdown.
 
Answer C Exam Level S CognitiveLevel Comprehension  Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier:(1) 032 Generic 2.1.12 Abdity to apply Technical Specifications to RO Group:  SRO Group: 2 a system.
 
RO K/A  SPO K/A 4.0 Reference Title Facility Reference Number Section Page Revision Learning Obj.
 
Technical Boron Dilution Alarm 3.3.111 3.3-111-1
        *3182 Specifcations Material Required for Examination Question Source: New i        l l
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1 Question #111 The following conditions exist on Unit 3:
-
Reactor power is 100%
-
At 1200 a known tube leak of 0.05 gpm exists in E089
-
At 1300 the leak increases to 0.075 gpm
-
At 1400 the leak increases to 0.090 gpm
-- At 1500 the leak increases to 0.12 gpm
--
Secondary radiation monitor msponse confirms increases What action, if any, is required as a result of the increasing S/G tube leak as directed by SO23-13-14 " Reactor Coolant leak"?
A. Operation of the unit can continue. l B. The reactor should be tripped immediately.
 
C. A rapid shutdown must be initiated.
 
D. . A controlled shutdown must be completed within 6 hours.
 
Answer D Exam Level S Cognitive Level Applicaten Facility San Onofre 2 & 3 Exam Date 4/16/99 4 Tier: (1) 037 AA2.05 Past history of leakage wth current problem RO Group:  SRO Group: 2 RO K/A  SRO K/A 3.3 Reference Title Facility Reference Number Section Page Revision Learning Obj.
 
Reactor Cootant Leak SO23-13-14  3.4.7.5 15 2  6574 Material Required for Examination      i Question Source: NRC 11/98 j
 
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Question #112 During coastdown prior to a refueling outage, system frequency increases to 60.5 henz. How will the RCS respond?
A. Temperature increases, pressure increases.
 
B. Temperature increases, pressure decreases.
 
C. Temperature decreases, pressure decreases.
 
D. Temperature decreases, pressure increases.
 
Answer A- Exam Level S Cognitive Level Application Facility San Onofre 2 & 3 Exam Date 4/1693 Tier:(2) 039 K5.08 Effoct of steam removal on reactivity RO Group:  SRO Group: 2 RO K/A  SRO K/A 3.6 Reference Title Facility Reference Number Section Page Revision Learning Obj.
 
Genere Fundamentals    , 4354
' Material Required for Examination Question Source: New i
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Question #113 l Unit 2 is operating at full power when a loss of 125VDC Bus 2D5 occurs.
 
l What effect does this have on the Unit 2 Turbine / Generator?
'A. A main generator automatic trip will occur.
 
'
B. The turbine will trip on overspeed.
 
C. The turbine emergency oil pump motors will lose power.
 
D. The Turbine Stop and Governor valves will go closed.
 
Answer D Exam Level S Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier. (1) 058 AA2.03 DC loads lost; impact on abihty to operate and RO Group:  SRO Group: 2 monitor plant systems.
 
RO K/A  SRO K/A 3.9 Refe ence Title Facihty Reference htmber Section Page Revision Leaming Obj.
 
Operation of 125 VDC SO234-15  Att.13 71 13 g[gg Systems Material Required for Examination Question Source: NRC i1/98
 
!
1^
Question #114 Which of the following is the correct response if an Emergency Diesel Generator (EDG) is paralleled to the grid and both the governor and voltage control pushbuttons are taken to
" Raise"?
A. EDG KW increases and EDG speed increases.
 
B. EDG reactive load increases and EDG KW increases.
 
C. EDG frequency increases and EDG reactive load increases.
 
D. EDG speed increases and EDG frequency increases.
 
Answer B Exam Level B Cognitive Level Comprehension Facihty San Onofre 2 & 3 Exam Date 4/16/99 Tier:(2) 062 A1.01 Signifcance of D/G load limits RO Group: 2 SRO Group: 2 RO K/A 3.4 SRO K/A 3.8 Reference Title Facihty Reference Number Section Page Revision Learning Obj.
 
Diesel Generator SO23-3-3.23  Att.1 21 14 7152 Monthly Test Material Required for Examination      .
Question Source: New      l
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l Question #115 The Control Room has been evacuated due to a toxic chemical hazard inside the Control Room envelope. Shutdown fmm outside of the Control Room, SO23-13-2 is in progress:
At the EPPM L-411:
  -> SG E-088 Wide Range level, LI-l 106 indicates 55%
  - RCS Teold, indicates 530 F RCS Thot, indicates 548'F
  '
  -
  -
S/G pressure indicates 900 psia Determine the actual water level in steam generator E-088.
 
A. 35 %
B. 48 %
C. 58E t
D. 75 %
Answer C Exam Level S Cognitive Level Applicaton Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (1) 068 1.03 S/G level  RO Group:  SRO Group: 1 ,
RO K/A  SRO K/A 4.3 Reference Title Facility Reference Number Section Page Revision Learnirg Obj.
 
Shutdown from Outside SO23-13-2  Att. 4 35 5 the Control Room 63025 Material Required for Examination SO23-13-2, Attachment 4 Question Source: Bank
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Question #116 The following conditions exist during a Unit 2 refueling:
-
Core offload is in progress
-
Steam Generator E089 is being sludge lanced
-
An operator reports that Main Steam Relief Header Drain Valve, S2130lMU394, on S/G E089 is removed Which of the following actions is required?
A. Restore Containment Integrity within one hour.
 
i B. Suspend Core Alterations.
 
\
C. Initiate Manual Containment Purge Isolation Signal.
 
D. Verify containment leakage is within specifications.
 
.
.
Answer B Exam Level S Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (1) 069 aal.01 Isolation valves, dampers and RO Group:  SRO Group: 1 ,
Mr. Truman Burns \Mr Robert Kinosian Califomia Public Utilities Commission 505 Van Ness, Rm. 4102 San Francisco, California 94102
electropneumatic devices l
_ _ _ _ - . _O
RO K/A  SR O K/A 3.7 Reference Tnie Facility Reference Number Section Page Revision Learning Obj.
 
Technical Containment Penetrations 3.9.3 3.94  777g Specifcations      j j
Material Required for Examination      ;
Question Source: Bank i
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r Question #117 Given the following plant conditions:
-
Unit 2 is at 20% power
-
Tc is currently at 534 F Which of the following does the Technical Specifications require?
A. - Perform SR 3.4.2.1.
 
B. Enter LCO 3.4.I Condition C.
 
C. Enter LCO 3.4.2 Condition A.
 
D. Perform SR 3.4.3.1 Answer A Exam Level S Cognitive Level Application Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: 2.1.33 Ability to recognize indications for system operating parameters RO Group:  SRO Group:
which are entry level conditions for Technical Specif cations.
 
RO K/A  SRO K/A 4.0 Reference Title Facility Rete./ence Number Section Page Revision Learning Obj.
 
Technical  RCS Minimum Temperature 3.42 3.4-4  g3g Specifcations for Cr ticality Material Required for Examination: T.S.s 3.4.1,3.4.2,3.4.3 (Bases not required)
Question Source: Bank
        ;
I l        A E_
 
p Question #118 Given the following plant conditions:
-
The Unit is in MODE 1.
 
-
The Spent Fuel Pool Boron Concentration is 1825 ppm. 1
-
Actions are being taken to restore boron concentration.
 
l i
Which of the following states an additional required action for this condition?
A. Direct HP to perform a radiation survey.
 
B. Install a local Criticality Accident Radiation Monitor.
 
C. Initiate a manual Fuel Handling Isolation Signal.
 
'
D. Suspend mcvement of fuel in the Spent Fuel Pool.
 
Answer D - Exam Level S Cognitive level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: 2.2.31 Knowledge of SRO fuel handling responsibilities RO Group:  SRO Group:
RO K/A  SRO K/A 3.8 Reference Title Facility Reference Number Secton Page Revision Learning Obj.
 
Techncal  Fuel Storage Pool Boron 3.7.17 3.7-30 Specifcatons Concentraton 7949 Material Required for Examination Question Source: Bank
        ,
f a
 
l
[
Question #119 A Gaseous Effluent Release Permit requires a Weather Evaluation prior to the release. The following meteorologi. cal conditions exist:
  -
Wind direction is 210 degrees
  -
Temperature difference between 10 and 40 meters is minus 0.26 C
  -
X/Q value is <4.8E-6
        !
l Determine the MINIMUM wind speed which would allow the release to be commenced. 1 A. 44 mph.
 
B. 69 mph.
 
*
C. 82 mph,      I!
D. 100 mph.
 
.
Answer B Exam Lovel S Cognitive Level Apphcation Facility San Onotre 2 & 3 Exam Date 4/16/99
 
Tier: 2.3.11 Abihty to control radiaton releases RO Group:  SRO Group:
RO K/A  SRO K/A 3 2 Reference Title Facility Reference Number Sertion Page Revision ' Learning Obj. l Radwaste Gas SO23-8-15  Att. 4 35 11 6268 Discharge        ,
I Material Required for Examination: SO23-8-15 Attachment 4 Question Source: NRC 6/98      i i
 
l
 
I i
        !
l l.
 
l
        ;
l        4 L        j
 
Question #120 Unit 2 is in MODE 5 on Shutdown Cooling.
 
- While maintenance was being performed on I TOP isolation valve 2HV9339, the valve
. packing failed.
 
- Pressurizer level is lowering with the only available charging pump running.
 
- The loss of SDC AOI has been entered and a llPSI pump has been started to restore level.
 
- liPSI pump flow required to maintain Pressurizer level is 150 gpm.
 
Which of the following is the correct Emergency Event Classification?
A. None apply.
 
B. B3-1.
 
C. G1-1.
 
D. B2- 1.
 
Answer C Exam Level S Cognitive Level Apphcation Facildy San Onofre 2 & 3 Exam Date 4/16/99 Tier: 2.4.29 Knowledgeof theemergencyplan  RO Group:  SRO Group:
i RO K/A  SRO K/A 4.0 Reference Title Facihty Reference Number Section Page Revision Learning Obj.
 
EPIP  SO123-Vill-1  Att. 2 50 11 17479 Material Required for Examination: sol 23-Vill-1 Attachment 2 Question Source: New      j l
 
[
l        l
\        1 l
l
    .
.
!
h L
i I
L        j
 
r Question #121 Unit 2 reactor has tripped. 'Ihe Control Room is being evacuated due to dense smoke.
 
.-
Which of the following correctly identifies the order in which the "lMMEDIATE ACTIONS" for Shutdown From Outside the Control Room AOI, SO23-13-2 are to be completed?
A. l.) Manually initiate MSIS 2.) Stop all RCPs 3.) Select manual and stop all Charging Pumps B. l.) Select manual and stop all Charging Pumps 2.) Manually initiate MSIS 3.) Stop all RCPs
 
i C. l.) Manually initiate MSIS 2.) Select manual and stop all Charging Pumps    ,
l 3.) Stop all RCPs l
l  D. l.) Stop all RCPs 2.) Manually initiate MSIS
'
3.) Select manual and stop all Charging Pumps Answer C Exam Level S - Cognitive Level Memory  Facility San Onotre 2 & 3 Exam Date 4/16/99 !
Tier: 2.4.49 ' Abihty to perform wthout reference to procedures those RO G.oup:  SRO Group:
actions that require immediate operation of system (
components and controls l
I      RO K/A  SRO K/A 4.0
!
l
'
Reference Title Facility Reference Number Section Page Revision Leamino Obj.
 
Shutdown from Outside SO23-13-2  2.0 2 5  6460 the Control Room I
!
- Material Required for Examination      !
Question Source: Bank
    .
        (
- _ .
 
Question #122 Given the following:
-
A reactor trip has occurred from 100% power
--
All systems have responded normally
-
No operator actions have occurred
-
The following conditions are observedi RCS temperature is 545*F and stable
  -
Both S/G levels are 35% NR and rising
  -
Both S/G pressures are 1000 psia and stable Given these conditions, which of the following statements correctly describes the feedwater configuration to the S/Gs?
A. MFW only is supplying feedwater to both S/Gs.
 
B. AFW only is supplying feedwater to both S/Gs.
 
C. MFW and AFW are both supplying feedwater to both S/Gs.
 
D. No feedwater is being supplied to the S/Gs. AFW will have to be manually aligned to supply feedwater.
 
Answer A Exam Level S CognitiveLevel Application Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier:(1) CE/E02 ek22 Facility's heat removal systems, including : RO Group:  SRO Group: 2 primary coolant, emergency coolant, the decay heat removal systems and relations between the proper operat.on of these systems to the operation of the facility RO K/A  SRO K/A 4.0 Reference Title Facility Reference Number Section Page Revision Learning Obj.
 
Reactor Trip Recovery SO23-12-2  5 13 6509 Material Required for Examination Question Source: Bank L        -
 
p
.
Question #125 Given the following plant conditions:
  -
Per SO23-12-1, SPTAs, a LOCA has been identified
, -
Pressurizer pressure is 1250 psia
-
Pressurizer levelis 100%
-
HPSIinjection valves are fully open
-
RCS is 17 F subcooled-
-
RVLMS indicates 100% in plenum and 48% in upper F.ead
-
No RCP's are running
-
Containment temperature and pressuie are 195 F and 1i psig, respectively
- SIAS, CIAS, MSIS and CSAS have actuated
-
A cooldown is in progress using steam generators Which of the following actions should be directed by the CRS?
A. Throttle HPSI flow to allow depressurization of the primary system.
 
B. Throttle HPSI flow to restore pressurizer level to program.
 
C. Continue maximum injection flow until subcooling is restored.
 
D. Continue maximum injection flow until the RVLMS indicates the upper head is full.
 
Answer C Exam Level S Cognitive Level Application Facility San Onofra 2 & 3 Exam Date 4/16/99 Tier:(1) W/E11 ek22 Facility's heat removal systems, including RO Group:  SRO Group: 2 primary coolant. emergency coolant, the decay heat removal systems and relations between the proper operation of these systems to the operation of the facility.
 
RO K/A  SRO K/A 4.3 Reference Title Facility Reference Number Section Page Revision Learning Obj.
 
LOCA Bases SO23-14-3  Att.1 48 4 6511 Material Required for Examination:
Question Source: Bank-
:
,
        ,
}}
}}

Revision as of 19:48, 19 November 2020

Informs That During 990112 Telcon Between Mk Rauch & J Pellet,Arrangements Were Made for Administration of Written Retake License Exams 50-361/99-301 & 50-362/99-301 at San Onofre,During Wk of 990308
ML20199E879
Person / Time
Site: San Onofre  Southern California Edison icon.png
Issue date: 01/13/1999
From: Pellet J
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To: Ray H
SOUTHERN CALIFORNIA EDISON CO.
References
50-361-99-301, 50-362-99-301, NUDOCS 9901210109
Download: ML20199E879 (4)
v • d • e


Text

._. . . __ -. . . - -

I

  1. ' "'44 9 UNITED STATES

[f ,

t ,

NUCLEAR REGULATORY COMMISSION

$ f REGloN IV 611 RYAN PLAZA drive, SUITE 400

y g ARLINGTON, texas 76011-8064 January 13,1999 l Harold B. Ray, Executive Vice President Southern California Edison Co.

San Onofre Nuclear Generating Station P.O. Box 128 San Clemente, California 92674-0128 SUBJECT: NRC INSPECTION REPORT 50-361/99-301; 50-362/99-301

Dear Mr. Ray:

In a telephone conversation on January 12,1999, between Messrs. K. Rauch and J. Pellet, j arrangements were made for the administration of written retake licensing examinations at San

, Onofre, during the week of March 8,1999.

As agreed during the telephone conversation, your staff will prepare the examinations based on the guidelines in Revision 8, of NUREG-1021," Operator Licensing Examination Standards for Power Reactors." The NRC regional office will discuss with your staff any changes that might be necessary before the examinations are administered.

,

To meet the above schedule, it will be necessary for your staff to furnish the examination outlines by January 21,1999. The written examinations and the supporting reference

'

materials identified in Attachment 2 of ES-201 will be due by March 1,1999. Any delay in j

receiving the required examination and reference materials, or the submittal of inadequate or incomplete materials, may cause the examinations to be rescheduled.  ;

l in order to conduct the requested written examinations, it will be necessary for your staff to l provide adequate space and accommodations in accordance with ES-402.

Appendix E of NUREG-1021 contains a number of NRC policies and guidelines that will be in effect while the written examinations are being administered.

To permit timely NRC review and evaluation, your staff should submit preliminary reactor l

'

operator and senior reactor operator license applications (Office of Management and Budget (OMB) approval number 3150-0090), medical certifications (OMB approval number 3150-0024),

and waiver requests (if any) (OMB approval number 3150-0090) at least 30 days before the first examination date. If the applications are not received at least 30 days before the examination l

i date, a postponement may be necessary. Signed applications certifying that all training has been completed should be submitted at least 14 days before the first examination date.

.

9901210109 990113 l PDR ADOCK 05000361 y PDR l

.

l San Onofre Nuclear Generating Station -4- l E-Mail report to T. Frye (TJF)

E-Mail report to D. Lange (DJL)

E-Mail report to NRR Event Tracking System (IPAS)

E-Mail report to Document Control Desk (DOCDESK)

/

bec to DCD (IE01) - DRS, DRP, and Decommissioning d

bec distrib. by RIV:

Regional Administrator DRS Director -

Resident inspector DRP Director DRS-PSB DRS Director MIS System

'

Branch Chief (DRP/E)

RIV File Senior Project inspector (DRP/E)

Branch Chief (DRP/TSS)

DOCUMENT NAME: R:\_SO23\SO930111.]lp To receive copy of document, Indicate in box: "C' = Copy without enclosures *E' = Copy with enclosures "N* = No copy l ' C:OB l@- D:DRP l l l l JLPellet/imb6 " '

KEBrockmanW 01/fV99 01/tV99 OFFICIAL RECORD COPY ,

,

!

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u

.)

l l

San Onofre Nuclear Generating Station -2-  !

This letter contains information collections that are subject to t' e oapenvork Reduction Act of 1995(44 U.S.C. 3501 et seq.). These information collections v ro approved by the Office of Management and Budget, approval number 3150-0101, which apires on April 30,2000. l The public reporting burden for this collection of information iu a stiraated 'o average 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> per response, including the time for reviewing instructions, gttherilj ar.d maintaining the data needed, writing the examinations, and completing and reviewinl1 ti e collection of in'ormation.

Send comments on any aspect of this collection of information, oc i hg suggestions for reducing the burden, to the information and Records Managemen' Branch E-6 F33), U.S.

Nuclear Regulatory Commission, Washington, DC 20555-0001, or isy !nte'ne; ?lectronic mail at BJS1 @NRC. GOV; and to the Desk Officer, Office of Information and Regulatory Affairs,  !

NEOB-10202, (3150-0101), Office of Management and Budget, Washington, DC 20503.

The NRC may not conduct or sponsor, and a person is not required to respond to, a collection I of information unless it displays a currently valid OMB control number.

l Thank you for your cooperation in this matter. Mr. Rauch has been advised of the policies and guidelines referenced in this letter. If you have any questions regarding the i 1C's examination

, procedures and guidelines, please contact me.

Sincerely, cLM*

John L. Pellet, Chief

"

Operations Branch l Division of Reactor Safety Docket Nos.: 50-361;50-362

.

License Nos.: NPF-10; NPF-15 cc:

,

Chairman, Board of Supervisors County of San Diego

,

J l

1600 Pacific Highway, Room 335 l San Diego, California 92101 l

% s R. Watts, Esq.

<etodruff, Spradlin & Smart 7T S. Parker St. Suite 7000 Ora ige, Califomia 92868-4720 /

s Sherwin Harris, Resource Project Manager Public Utilities Department l City of Riverside 3900 Main Street Riverside, California 92522

_

-

,_ _ i San Onofre Nuclear Generating Station -3-R. W. Krieger, Vice President Southem California Edison Company San Onofre Nuclear Generating Station P.O. Box 128 San Clemente, California 92674-0128

. Stephen A. Woods, Senior Health Physicist Division of Drinking Water and Environmental Management Nuclear Emergency Response Program Califomia Department of Health Services P.O. Box 942732, M/S 396 Sacramento, California 94334-7320 Mr. Michael R. Olson Sr. Energy Administrator-

. San Diego Gas & Electric Company P. O. Box 1831

,

San Diego, Califomia 92112-4150 Mr. Steve Hsu Radiological Health Branch State Department of Health Services P.O. Box 942732 Sacramento, California 94234

<

Mayor City of San Clemente 100 Avenida Presidio San Clemente, California 92672

.

Mr. Truman Burns \Mr Robert Kinosian Califomia Public Utilities Commission 505 Van Ness, Rm. 4102 San Francisco, California 94102

_ _ _ _ - . _O

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